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Note: This page contains sample records for the topic "tube project decommissioning" from the National Library of EnergyBeta (NLEBeta).
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1

Shippingport Station Decommissioning Project decommissioning plan. Volume I  

SciTech Connect

Information is presented concerning the organization of the decommissioning project; decommissioning operations concept; safety and environmental assessment; information and guidance for the DOC; work breakdown structure; decommissioning operation schedule; decommissiong operations estimate; and training requirements.

Not Available

1983-09-01T23:59:59.000Z

2

Shippingport Station decommissioning project decommission plan  

SciTech Connect

This volume consists of the following appendices: long-lead-time activities, technical baseline, assessment of one-price removal of reactor vessel and internals by barge, final environmental impact statement (this forms the bulk of this volume), and record of the decision to decommission Shippingport. (DLC)

Not Available

1983-01-01T23:59:59.000Z

3

West Valley Demonstration Project Phase I Decommissioning - Facility  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Project Phase I Decommissioning - Project Phase I Decommissioning - Facility Disposition Partnering Performance Agreement West Valley Demonstration Project Phase I Decommissioning - Facility Disposition Partnering Performance Agreement The Department of Energy, West Valley Demonstration Project (DOE-WVDP) and CH2M Hill B&W West Valley (CHBWV) are committed to continuous improvement and will utilize principles of the DOE Environmental Management (DOE-EM) Partnering Policy to create and foster a team environment to successfully complete the West Valley Demonstration Project (WVDP) Phase I Decommissioning - Faciltiy Disposition. West Valley Demonstration Project Phase I Decommissioning - Facility Disposition Partnering Performance Agreement More Documents & Publications CX-009527: Categorical Exclusion Determination

4

Safety analysis for Shippingport Station Decommissioning Project. Vol. 9. Pt. 1. Rev. 1  

SciTech Connect

Information is presented concerning the safety analysis for the decommissioning project; and permitting plan.

Not Available

1983-09-01T23:59:59.000Z

5

Idaho Site Closes Out Decontamination and Decommissioning Project about  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Site Closes Out Decontamination and Decommissioning Project Site Closes Out Decontamination and Decommissioning Project about $440 Million under Cost Idaho Site Closes Out Decontamination and Decommissioning Project about $440 Million under Cost November 8, 2012 - 12:00pm Addthis Workers demolish the Test Area North Hot Shop Complex, shown here. Workers demolish the Test Area North Hot Shop Complex, shown here. Crews demolish CPP-601, a building used during used nuclear fuel reprocessing at the Idaho Nuclear Technology and Engineering Center. Crews demolish CPP-601, a building used during used nuclear fuel reprocessing at the Idaho Nuclear Technology and Engineering Center. The Engineering Test Reactor vessel is shown here removed, loaded and ready for transport to the on-site landfill. The Engineering Test Reactor vessel is shown here removed, loaded and ready

6

DOE Awards Contract for Decontamination & Decommissioning Project for the  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

DOE Awards Contract for Decontamination & Decommissioning Project DOE Awards Contract for Decontamination & Decommissioning Project for the East Tennessee Technology Park DOE Awards Contract for Decontamination & Decommissioning Project for the East Tennessee Technology Park April 29, 2011 - 12:00pm Addthis Media Contact Mike Koentop (865) 576-0885 www.oakridge.doe.gov Oak Ridge, Tenn. - As part of its ongoing commitment to cleaning up the legacy of the Cold War at sites across the weapons complex, the U.S. Department of Energy has awarded a contract for the remaining environmental cleanup at the East Tennessee Technology Park (ETTP) to URS | CH2M Oak Ridge, LLC. The $2.2 billion contract will complete cleanup and provide support functions at ETTP, while supporting local jobs and area small businesses. "Today's contract announcement means that we can continue to meet our

7

DOE Awards Contract for Decontamination & Decommissioning Project for the  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Decontamination & Decommissioning Project Decontamination & Decommissioning Project for the East Tennessee Technology Park DOE Awards Contract for Decontamination & Decommissioning Project for the East Tennessee Technology Park April 29, 2011 - 12:00pm Addthis Media Contact Mike Koentop (865) 576-0885 www.oakridge.doe.gov Oak Ridge, Tenn. - As part of its ongoing commitment to cleaning up the legacy of the Cold War at sites across the weapons complex, the U.S. Department of Energy has awarded a contract for the remaining environmental cleanup at the East Tennessee Technology Park (ETTP) to URS | CH2M Oak Ridge, LLC. The $2.2 billion contract will complete cleanup and provide support functions at ETTP, while supporting local jobs and area small businesses. "Today's contract announcement means that we can continue to meet our

8

DOE EM Project Experience & Lessons Learned for In Situ Decommissioning  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

EM Project Experience & Lessons Learned for In Situ EM Project Experience & Lessons Learned for In Situ Decommissioning (Feb. 2013) DOE EM Project Experience & Lessons Learned for In Situ Decommissioning (Feb. 2013) The purpose of the "DOE EM Project Experience & Lessons Learned for In Situ Decommissioning" report is to capture the considerable technical experience gained to date for implementation of In Situ Decommissioning (ISD) projects at DOE facilities. As current and projected budgets for the EM program indicate reduced and flat funding profiles for the foreseeable future, the potential exists for this institutional knowledge to be lost as the ramp-down of project staffing commences with the cessation of ARRA. EM's Office of Deactivation & Decommissioning and Facility Engineering

9

PROJECT MANGEMENT PLAN EXAMPLES Deactivation to Decommissioning Transition  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

to Decommissioning Transition to Decommissioning Transition Example Example 80 1.5 OPERATIONAL TRANSITION AND DEACTIVATION STRATEGY According to the U.S. Department of Energy (DOE) Order 430.1A Life Cycle Asset Management (LCAM), the life cycle of a facility makes several transitions over the course of it's existence. The typical stages or phases include operation, (standby), deactivation, S&M, decontamination and decommissioning (D&D). The life cycle phases may occur as a straight through process or with long interim periods. In Fig. 1.4, "Facility Disposition Scenarios and Associated Hazard Profiles" (Ref. DOE-STD-1120-98), Scenario 2 demonstrates the life cycle phasing that most closely represents that of the 9206 Complex. Since the ultimate disposition of Building 9206 (and associated buildings and operations) is not known, a decision was made to

10

INDEPENDENT VERIFICATION SURVEY OF THE HIGH FLUX BEAM REACTOR DECOMMISSIONING PROJECT OUTSIDE AREAS BROOKHAVEN NATIONAL LABORATORY UPTON, NEW YORK  

SciTech Connect

5098-SR-03-0 FINAL REPORT- INDEPENDENT VERIFICATION SURVEY OF THE HIGH FLUX BEAM REACTOR DECOMMISSIONING PROJECT OUTSIDE AREAS, BROOKHAVEN NATIONAL LABORATORY

P.C. Weaver

2010-12-15T23:59:59.000Z

11

LETTER REPORT INDEPENDENT VERIFICATION OF THE HIGH FLUX BEAM REACTOR DECOMMISSIONING PROJECT FAN HOUSE, BUILDING 704 BNL  

SciTech Connect

5098-LR-01-0 -LETTER REPORT INDEPENDENT VERIFICATION OF THE HIGH FLUX BEAM REACTOR DECOMMISSIONING PROJECT FAN HOUSE, BUILDING 704 BROOKHAVEN NATIONAL LABORATORY

P.C. Weaver

2010-10-22T23:59:59.000Z

12

Action Memorandum for General Decommissioning Activities under the Idaho Cleanup Project  

SciTech Connect

This Action Memorandum documents the selected alternative to perform general decommissioning activities at the Idaho National Laboratory (INL) under the Idaho Cleanup Project (ICP). Preparation of this Action Memorandum has been performed in accordance with the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), as amended by the "Superfund Amendments and Reauthorization Act of 1986", and in accordance with the "National Oil and Hazardous Substances Pollution Contingency Plan". An engineering evaluation/cost analysis (EE/CA) was prepared and released for public comment and evaluated alternatives to accomplish the decommissioning of excess buildings and structures whose missions havve been completed.

S. L. Reno

2006-10-26T23:59:59.000Z

13

Interim Status of the Accelerated Site Technology Deployment Integrated Decontamination and Decommissioning Project  

SciTech Connect

The Idaho National Engineering and Environmental Laboratory (INEEL), Fernald Environmental Management Project (FEMP), and Argonne National Laboratory - East (ANL-E) teamed to establish the Accelerated Site Technology Deployment (ASTD) Integrated Decontamination and Decommissioning (ID&D) project to increase the use of improved technologies in D&D operations. The project is making the technologies more readily available, providing training, putting the technologies to use, and spreading information about improved performance. The improved technologies are expected to reduce cost, schedule, radiation exposure, or waste volume over currently used baseline methods. They include some of the most successful technologies proven in the large-scale demonstrations and in private industry. The selected technologies are the Pipe Explorer, the GammaCam, the Decontamination Decommissioning and Remediation Optimal Planning System (DDROPS), the BROKK Demolition Robot, the Personal Ice Cooling System (PICS), the Oxy-Gasoline Torch, the Track-Mounted Shear, and the Hand-Held Shear.

A. M Smith; G. E. Matthern; R. H. Meservey

1998-11-01T23:59:59.000Z

14

Impact of Lack of Consistent Free Release Standards on Decommissioning Projects and Costs  

SciTech Connect

While the Nuclear Regulatory Commission has had specific and dose-based standards for the release of liquids and gases for a long time, there are no regulatory mechanisms in place for the release of solid bulk materials from a nuclear power plant. Even though free releases of small quantities of solid materials continue under existing guidelines from the operating plants, the regulatory void creates major difficulties for the bulk materials that result from the decommissioning of a nuclear site. Decommissioning of a commercial nuclear power plant generates large quantities of solid bulk materials such as concrete, metal, and demolition debris. Disposition of such materials has a large impact on the overall decommissioning cost. Yet, there are no clear and cost-effective alternatives for the disposal of these materials from a regulatory perspective. This paper discusses the methodologies for clearance of solid materials1, their applicability to the disposition of bulk materials, and the impact of lack of consistent free release standards on the decommissioning projects and costs.

Devgun, J. S.

2002-02-26T23:59:59.000Z

15

Decommissioning Plan RM  

Energy.gov (U.S. Department of Energy (DOE))

The Decommissioning Plan Review (DPR) Module is a tool that assists DOE federal project review teams in evaluating the adequacy of the decommissioning plan prior to approval of the associated CD.

16

The Windscale Advanced Gas Cooled Reactor (WAGR) Decommissioning Project A Close Out Report for WAGR Decommissioning Campaigns 1 to 10 - 12474  

SciTech Connect

The reactor core of the Windscale Advanced Gas-Cooled Reactor (WAGR) has been dismantled as part of an ongoing decommissioning project. The WAGR operated until 1981 as a development reactor for the British Commercial Advanced Gas cooled Reactor (CAGR) power programme. Decommissioning began in 1982 with the removal of fuel from the reactor core which was completed in 1983. Subsequently, a significant amount of engineering work was carried out, including removal of equipment external to the reactor and initial manual dismantling operations at the top of the reactor, in preparation for the removal of the reactor core itself. Modification of the facility structure and construction of the waste packaging plant served to provide a waste route for the reactor components. The reactor core was dismantled on a 'top-down' basis in a series of 'campaigns' related to discrete reactor components. This report describes the facility, the modifications undertaken to facilitate its decommissioning and the strategies employed to recognise the successful decommissioning of the reactor. Early decommissioning tasks at the top of the reactor were undertaken manually but the main of the decommissioning tasks were carried remotely, with deployment systems comprising of little more than crane like devices, intelligently interfaced into the existing structure. The tooling deployed from the 3 tonne capacity (3te) hoist consisted either purely mechanical devices or those being electrically controlled from a 'push-button' panel positioned at the operator control stations, there was no degree of autonomy in the 3te hoist or any of the tools deployed from it. Whilst the ATC was able to provide some tele-robotic capabilities these were very limited and required a good degree of driver input which due to the operating philosophy at WAGR was not utilised. The WAGR box proved a successful waste package, adaptable through the use of waste box furniture specific to the waste-forms generated throughout the various decommissioning campaigns. The use of low force compaction for insulation and soft wastes provided a simple, robust and cost effective solution as did the direct encapsulation of LLW steel components in the later stages of reactor decommissioning. Progress through early campaigns was good, often bettering the baseline schedule, especially when undertaking the repetitive tasks seen during Neutron Shield and Graphite Core decommissioning, once the operators had become experienced with the equipment, though delays became more pronounced, mainly as a result of increased failures due to the age and maintainability of the RDM and associated equipment. Extensive delays came about as a result of the unsupported insulation falling away from the pressure vessel during removal and the inability of the ventilation system to manage the sub micron particulate generated during IPOPI cutting operations, though the in house development of revised and new methodologies ultimately led to the successful completion of PV and I removal. In a programme spanning over 12 years, the decommissioning of the reactor pressure vessel and core led to the production 110 ILW and 75 LLW WAGR boxes, with 20 LLW ISO freight containers of primary reactor wastes, resulting in an overall packaged volume of approximately 2500 cubic metres containing the estimated 460 cubic metres of the reactor structure. (authors)

Halliwell, Chris [Sellafield Ltd, Sellafield (United Kingdom)

2012-07-01T23:59:59.000Z

17

Decontamination and decommissioning of the Experimental Boiling Water Reactor (EBWR): Project final report, Argonne National Laboratory  

SciTech Connect

The Final Report for the Decontamination and Decommissioning (D&D) of the Argonne National Laboratory - East (ANL-E) Experimental Boiling Water Reactor (EBWR) facility contains the descriptions and evaluations of the activities and the results of the EBWR D&D project. It provides the following information: (1) An overall description of the ANL-E site and EBWR facility. (2) The history of the EBWR facility. (3) A description of the D&D activities conducted during the EBWR project. (4) A summary of the final status of the facility, including the final and confirmation surveys. (5) A summary of the final cost, schedule, and personnel exposure associated with the project, including a summary of the total waste generated. This project report covers the entire EBWR D&D project, from the initiation of Phase I activities to final project closeout. After the confirmation survey, the EBWR facility was released as a {open_quotes}Radiologically Controlled Area,{close_quotes} noting residual elevated activity remains in inaccessible areas. However, exposure levels in accessible areas are at background levels. Personnel working in accessible areas do not need Radiation Work Permits, radiation monitors, or other radiological controls. Planned use for the containment structure is as an interim transuranic waste storage facility (after conversion).

Fellhauer, C.R.; Boing, L.E. [Argonne National Lab., IL (United States); Aldana, J. [NES, Inc., Danbury, CT (United States)

1997-03-01T23:59:59.000Z

18

Accelerating the Whiteshell Laboratories Decommissioning Through the Implementation of a Projectized and Delivery-Focused Organization - 13074  

SciTech Connect

Whiteshell Laboratories (WL) is a nuclear research site in Canada that was commissioned in 1964 by Atomic Energy of Canada Limited. It covers a total area of approximately 4,375 hectares (10,800 acres) and includes the main campus site, the Waste Management Area (WMA) and outer areas of land identified as not used for or impacted by nuclear development or operations. The WL site employed up to 1100 staff. Site activities included the successful operation of a 60 MW organic liquid-cooled research reactor from 1965 to 1985, and various research programs including reactor safety research, small reactor development, fuel development, biophysics and radiation applications, as well as work under the Canadian Nuclear Fuel Waste Management Program. In 1997, AECL made a business decision to discontinue research programs and operations at WL, and obtained government concurrence in 1998. The Nuclear Legacy Liabilities Program (NLLP) was established in 2006 by the Canadian Government to remediate nuclear legacy liabilities in a safe and cost effective manner, including the WL site. The NLLP is being implemented by AECL under the governance of a Natural Resources Canada (NRCan)/AECL Joint Oversight Committee (JOC). Significant progress has since been made, and the WL site currently holds the only Canadian Nuclear Safety Commission (CNSC) nuclear research site decommissioning license in Canada. The current decommissioning license is in place until the end of 2018. The present schedule planned for main campus decommissioning is 30 years (to 2037), followed by institutional control of the WMA until a National plan is implemented for the long-term management of nuclear waste. There is an impetus to advance work and complete decommissioning sooner. To accomplish this, AECL has added significant resources, reorganized and moved to a projectized environment. This presentation outlines changes made to the organization, the tools implemented to foster projectization, and the benefits and positive impacts on schedule and delivery. A revised organizational structure was implemented in two phases, starting 2011 April 1, to align WL staff with the common goal of decommissioning the site through the direction of the WL Decommissioning Project General Manager. On 2011 September 1, the second phase of the reorganization was implemented and WL Decommissioning staff was organized under five Divisions: Programs and Regulatory Compliance, General Site Services, Decommissioning Strategic Planning, Nuclear Facilities and Project Delivery. A new Mission, Vision and Objectives were developed for the project, and several productivity enhancements are being implemented. These include the use of an integrated and fully re-sourced Site Wide Schedule that is updated and reviewed at Plan-of-the-Week meetings, improved work distribution throughout the year, eliminating scheduling 'push' mentality, project scoreboards, work planning implementation, lean practices and various process improvement initiatives. A revised Strategic Plan is under development that reflects the improved project delivery capabilities. As a result of these initiatives, and a culture change towards a projectized approach, the decommissioning schedule will be advanced by approximately 10 years. (authors)

Wilcox, Brian; Mellor, Russ; Michaluk, Craig [Atomic Energy of Canada Limited, Whiteshell Laboratories, Pinawa, Manitoba (Canada)] [Atomic Energy of Canada Limited, Whiteshell Laboratories, Pinawa, Manitoba (Canada)

2013-07-01T23:59:59.000Z

19

Cost Estimating for Decommissioning of a Plutonium Facility--Lessons Learned From The Rocky Flats Building 771 Project  

SciTech Connect

The Rocky Flats Closure Site is implementing an aggressive approach in an attempt to complete Site closure by 2006. The replanning effort to meet this goal required that the life-cycle decommissioning effort for the Site and for the major individual facilities be reexamined in detail. As part of the overall effort, the cost estimate for the Building 771 decommissioning project was revised to incorporate both actual cost data from a recently-completed similar project and detailed planning for all activities. This paper provides a brief overview of the replanning process and the original estimate, and then discusses the modifications to that estimate to reflect new data, methods, and planning rigor. It provides the new work breakdown structure and discusses the reasons for the final arrangement chosen. It follows with the process used to assign scope, cost, and schedule elements within the new structure, and development of the new code of accounts. Finally, it describes the project control methodology used to track the project, and provides lessons learned on cost tracking in the decommissioning environment.

Stevens, J. L.; Titus, R.; Sanford, P. C.

2002-02-26T23:59:59.000Z

20

Factors Impacting Decommissioning Costs - 13576  

SciTech Connect

The Electric Power Research Institute (EPRI) studied United States experience with decommissioning cost estimates and the factors that impact the actual cost of decommissioning projects. This study gathered available estimated and actual decommissioning costs from eight nuclear power plants in the United States to understand the major components of decommissioning costs. Major costs categories for decommissioning a nuclear power plant are removal costs, radioactive waste costs, staffing costs, and other costs. The technical factors that impact the costs were analyzed based on the plants' decommissioning experiences. Detailed cost breakdowns by major projects and other cost categories from actual power plant decommissioning experiences will be presented. Such information will be useful in planning future decommissioning and designing new plants. (authors)

Kim, Karen; McGrath, Richard [Electric Power Research Institute, 3420 Hillview Ave., Palo Alto, California (United States)] [Electric Power Research Institute, 3420 Hillview Ave., Palo Alto, California (United States)

2013-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "tube project decommissioning" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


21

Decommissioning Unit Cost Data  

SciTech Connect

The Rocky Flats Closure Site (Site) is in the process of stabilizing residual nuclear materials, decommissioning nuclear facilities, and remediating environmental media. A number of contaminated facilities have been decommissioned, including one building, Building 779, that contained gloveboxes used for plutonium process development but did little actual plutonium processing. The actual costs incurred to decommission this facility formed much of the basis or standards used to estimate the decommissioning of the remaining plutonium-processing buildings. Recent decommissioning activities in the first actual production facility, Building 771, implemented a number of process and procedural improvements. These include methods for handling plutonium contaminated equipment, including size reduction, decontamination, and waste packaging, as well as management improvements to streamline planning and work control. These improvements resulted in a safer working environment and reduced project cost, as demonstrated in the overall project efficiency. The topic of this paper is the analysis of how this improved efficiency is reflected in recent unit costs for activities specific to the decommissioning of plutonium facilities. This analysis will allow the Site to quantify the impacts on future Rocky Flats decommissioning activities, and to develop data for planning and cost estimating the decommissioning of future facilities. The paper discusses the methods used to collect and arrange the project data from the individual work areas within Building 771. Regression and data correlation techniques were used to quantify values for different types of decommissioning activities. The discussion includes the approach to identify and allocate overall project support, waste management, and Site support costs based on the overall Site and project costs to provide a ''burdened'' unit cost. The paper ultimately provides a unit cost basis that can be used to support cost estimates for decommissioning at other facilities with similar equipment and labor costs. It also provides techniques for extracting information from limited data using extrapolation and interpolation techniques.

Sanford, P. C.; Stevens, J. L.; Brandt, R.

2002-02-26T23:59:59.000Z

22

Decommissioning at AWE  

SciTech Connect

AWE (A) has been at the heart of the UK Nuclear deterrent since it was established in the early 1950's. It is a nuclear licensed site and is governed by the United Kingdoms Nuclear Installation Inspectorate (NII). AWE plc on behalf of the Ministry of Defence (MOD) manages the AWE (A) site and all undertakings including decommissioning. Therefore under NII license condition 35 'Decommissioning', AWE plc is accountable to make and implement adequate arrangements for the decommissioning of any plant or process, which may affect safety. The majority of decommissioning projects currently being undertaken are to do with Hazard category 3, 4 or 5 facilities, systems or plant that have reached the end of their operational span and have undergone Post-Operational Clean-Out (POCO). They were either built for the production of fissile components, for supporting the early reactor fuels programmes or for processing facility waste arisings. They either contain redundant contaminated gloveboxes associated process areas, process plant or systems or a combination of all. In parallel with decommissioning project AWE (A) are undertaking investigation into new technologies to aid decommissioning projects; to remove the operative from hands on operations; to develop and implement modifications to existing process and techniques used. AWE (A) is currently going thorough a sustained phase of upgrading its facilities to enhance its scientific capability, with older facilities, systems and plant being replaced, making decommissioning a growth area. It is therefore important to the company to reduce these hazards progressively and safety over the coming years, making decommissioning an important feature of the overall legacy management aspects of AWE PLC's business. This paper outlines the current undertakings and progress of Nuclear decommissioning on the AWE (A) site. (authors)

Biles, K.; Hedges, M.; Campbell, C

2008-07-01T23:59:59.000Z

23

DECOMMISSIONING DOCUMENTS Decommissioning Handbook The Decommissioning Handbook has  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

DECOMMISSIONING DOCUMENTS DECOMMISSIONING DOCUMENTS Decommissioning Handbook The Decommissioning Handbook has been developed to incorporate examples and lessons learned, and to illustrate practices and procedures for implementing each step of the LCAM Decommissioning Implementation Guide. Decommissioning Benchmarking Study DOE's former Office of Environmental Restoration (EM-40) conducted a benchmarking study of its decommissioning program to analyze physical activities in facility decommissioning and to determine approaches to improve the decommissioning process. The study focused on quantifying productivity of decommissioning physical activities and identifying how productivity is affected by specific working conditions. The decommissioning benchmarking results are the foundation for several distinct products:

24

Decommissioning Documents | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Decommissioning Documents Decommissioning Documents More Documents & Publications Decommissioning Benchmarking Study Final Report Decommissioning Handbook dgappendices.pdf...

25

Decommissioning Handbook  

Energy.gov (U.S. Department of Energy (DOE))

The Decommissioning Handbook has been developed to incorporate examples and lessons learned, and to illustrate practices and procedures for implementing each step of the LCAM Decommissioing...

26

A Radiological Survey Approach to Use Prior to Decommissioning: Results from a Technology Scanning and Assessment Project Focused on the Chornobyl NPP  

SciTech Connect

The primary objectives of this project are to learn how to plan and execute the Technology Scanning and Assessment (TSA) approach by conducting a project and to be able to provide the approach as a capability to the Chernobyl Nuclear Power Plant (ChNPP) and potentially elsewhere. A secondary objective is to learn specifics about decommissioning and in particular about radiological surveying to be performed prior to decommissioning to help ChNPP decision makers. TSA is a multi-faceted capability that monitors and analyzes scientific, technical, regulatory, and business factors and trends for decision makers and company leaders. It is a management tool where information is systematically gathered, analyzed, and used in business planning and decision making. It helps managers by organizing the flow of critical information and provides managers with information they can act upon. The focus of this TSA project is on radiological surveying with the target being ChNPP's Unit 1. This reactor was stopped on November 30, 1996. At this time, Ukraine failed to have a regulatory basis to provide guidelines for nuclear site decommissioning. This situation has not changed as of today. A number of documents have been prepared to become a basis for a combined study of the ChNPP Unit 1 from the engineering and radiological perspectives. The results of such a study are expected to be used when a detailed decommissioning plan is created.

Milchikov, A.; Hund, G.; Davidko, M.

1999-10-20T23:59:59.000Z

27

Revised Draft Environmental Impact Statement for Decommissioning and/or Long-Term Stewardship at the West Valley Demonstration Project and Western New York Nuclear Service Center  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Environmental Impact Statement for Environmental Impact Statement for Decommissioning and/or Long-Term Stewardship at the West Valley Demonstration Project and Western New York Nuclear Service Center A Summary and Guide for Stakeholders DOE/EIS-0226-D (Revised) November 2008 The West Valley Site Availability of the Revised Draft EIS for Decommissioning and/or Long-Term Stewardship at the West Valley Demonstration Project and Western New York Nuclear Service Center For further information on this Draft EIS, or to request a copy please contact: Cathern Bohan, EIS Document Manager West Valley Demonstration Project U.S. Department of Energy Ashford Office Complex 9030 Route 219 West Valley, NY 14171 Telephone: 716-942-4159 Fax: 716-942-4703 E-mail: catherine.m.bohan@wv.doe.gov Printed with soy ink on recycled paper

28

Decommissioning handbook  

SciTech Connect

This document is a compilation of information pertinent to the decommissioning of surplus nuclear facilities. This handbook is intended to describe all stages of the decommissioning process including selection of the end product, estimation of the radioactive inventory, estimation of occupational exposures, description of the state-of-the-art in re decontamination, remote csposition of wastes, and estimation of program costs. Presentation of state-of-the-art technology and data related to decommissioning will aid in consistent and efficient program planning and performance. Particular attention is focused on available technology applicable to those decommissioning activities that have not been accomplished before, such as remote segmenting and handling of highly activated 1100 MW(e) light water reactor vessel internals and thick-walled reactor vessels. A summary of available information associated with the planning and estimating of a decommissioning program is also presented. Summarized in particular are the methodologies associated with the calculation and measurement of activated material inventory, distribution, and surface dose level, system contamination inventory and distribution, and work area dose levels. Cost estimating techniques are also presented and the manner in which to account for variations in labor costs as impacting labor-intensive work activities is explained.

Manion, W.J.; LaGuardia, T.S.

1980-11-01T23:59:59.000Z

29

Screening evaluation of radionuclide groundwater concentrations for the end state basement fill model Zion Nuclear Power Station decommissioning project  

SciTech Connect

ZionSolutions is in the process of decommissioning the Zion Nuclear Power Plant. The site contains two reactor Containment Buildings, a Fuel Building, an Auxiliary Building, and a Turbine Building that may be contaminated. The current decommissioning plan involves removing all above grade structures to a depth of 3 feet below grade. The remaining underground structures will be backfilled with clean material. The final selection of fill material has not been made.

Sullivan T.

2014-06-09T23:59:59.000Z

30

Decommissioning Plan RM  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Decommissioning Plan Review Module Decommissioning Plan Review Module March 2010 CD-0 O 0 C OFFICE OF D C CD-1 F ENVIRO Standard R Decomm Rev Critical Decisi CD-2 M ONMENTAL Review Plan missioning view Module ion (CD) Ap CD March 2010 L MANAGE n (SRP) g Plan e plicability D-3 EMENT CD-4 Post Oper ration Standard Review Plan, 2 nd Edition, March 2010 i FOREWORD The Standard Review Plan (SRP) 1 provides a consistent, predictable corporate review framework to ensure that issues and risks that could challenge the success of Office of Environmental Management (EM) projects are identified early and addressed proactively. The internal EM project review process encompasses key milestones established by DOE O 413.3A, Change 1, Program and Project Management for the Acquisition of Capital Assets, DOE-STD-1189-2008,

31

FINAL REPORT FOR INDEPENDENT CONFIRMATORY SURVEY SUMMARY AND RESULTS FOR THE HEMATITE DECOMMISSIONING PROJECT, FESTUS, MISSOURI  

SciTech Connect

ORAU conducted confirmatory surveys of the Hematite site during the period of June 12 through June 13, 2012. The survey activities included in-process inspections, document review, walkover surveys, sampling activities, and laboratory analysis of split samples. WEC was forthcoming with information relating to practices, procedures, and surface scan results. Scans performed by the WEC technician were extremely thorough and methodical. The WEC and ORAU technicians identified the same areas of elevated activity with comparable detector responses. WEC sampling of re-use soils, waste soils, sediments, and groundwater were conducted under ORAU observation. The sampling efforts observed by ORAU were performed in accordance with site-specific procedures and in a manner sufficient to provide quality supporting data. Three observations were made during groundwater sampling activities. First, the water level indicator was re-used without submitting rinse blank. Second, bubbles created during tubing extraction could indicate the presence of volatilized organic compounds. Third, samplers did not use a photo ionization detector prior to sample collection to indicate the presence of volatile organic vapors. Results of split samples indicated a high level of comparability between the WEC and ORAU/ORISE radiological laboratories. Analytical practices and procedures appear to be sufficient in providing quality radiochemical data. All concentrations from the Soil Re-Use Area and sediment samples are below Uniform radionuclide-specific derived concentration guideline level (DCGL{sub W}) limits; thus, comparisons to the less conservative stratified geometry were not required. Results were compared to individual DCGLs and using the sum of fractions approach. Both composite soil samples collected from the Waste Handling Area (Bins 1 and 4) were well below the prescribed USEI waste acceptance criteria.

Bailey, Erika N.; Lee, Jason D.

2012-09-21T23:59:59.000Z

32

Decontamination and decommissioning  

SciTech Connect

The project scope of work included the complete decontamination and decommissioning (D and D) of the Westinghouse ARD Fuel Laboratories at the Cheswick Site in the shortest possible time. This has been accomplished in the following four phases: (1) preparation of documents and necessary paperwork; packaging and shipping of all special nuclear materials in an acceptable form to a reprocessing agency; (2) decontamination of all facilities, glove boxes and equipment; loading of generated waste into bins, barrels and strong wooden boxes; (3) shipping of all bins, barrels and boxes containing waste to the designated burial site; removal of all utility services from the laboratories; and (4) final survey of remaining facilities and certification for nonrestricted use; preparation of final report. These four phases of work were conducted in accordance with applicable regulations for D and D of research facilities and applicable regulations for packaging, transportation, and burial and storage of radioactive materials. The final result is that the Advanced Fuel Laboratories now meet requirements of ANSI 13.12 and can be released for unrestricted use. The four principal documents utilized in the D and D of the Cheswick Site were: (1) Plan for Fully Decontaminating and Decommissioning, Revision 3; (2) Environmental Assessment for Decontaminating and Decommissioning the Westinghouse Advanced Reactors Division Plutonium Fuel Laboratories, Cheswick, Pa.; (3) WARD-386, Quality Assurance Program Description for Decontaminating and Decommissioning Activities; and (4) Health Physics, Fire Control, and Site Emergency Manual. These documents are provided as Attachments 1, 2, 3 and 4.

Adams, G.A.; Bowen, W.C.; Cromer, P.M.; Cwynar, J.C.; Jacoby, W.R.; Woodsum, H.G.

1982-02-01T23:59:59.000Z

33

ANL CP-5 decontamination and decommissioning project necessary and sufficient pilot. Report of the standards identification team on the selection of the necessary and sufficient standards set  

SciTech Connect

The CP-5 reactor was a heavy-water moderated and cooled, highly-enriched uranium-fueled thermal reactor designed for supplying neutrons for research. The reactor was operated almost continuously for 25 years until its final shutdown in 1979. It is situated on approximately three acres in the southwestern section of Argonne National Laboratory. In 1980, all nuclear fuel and the heavy water that could be drained from the process systems were shipped off-site, and the CP-5 facility was placed into lay-up pending funding for decommissioning. It was maintained in the lay-up condition with a minimum of maintenance until 1990, when the decontamination and decommissioning (D and D) project began. This D and D project provides for the disassembly and removal of all radioactive components, equipment, and structures that are associated with the CP-5 facility. The experimental area around the CP-5 reactor has been prepared for D and D, and the area outside the facility has been remediated. The reactor primary coolant and support systems have been removed and packaged as waste. The significant remaining tasks are (1) removal of the reactor internals and the biological shield structure; (2) decontamination of the rod storage area; (3) decontamination of the various radioactive material storage and handling facilities, including the fuel pool; and (4) decontamination and dismantlement of the building. This report describes the scope of the project, identification of standards for various aspects of the project, the lessons learned, and consideration for implementation.

NONE

1996-05-01T23:59:59.000Z

34

Interim Storage Facility decommissioning. Final report  

SciTech Connect

Decontamination and decommissioning of the Interim Storage Facility were completed. Activities included performing a detailed radiation survey of the facility, removing surface and imbedded contamination, excavating and removing the fuel storage cells, restoring the site to natural conditions, and shipping waste to Hanford, Washington, for burial. The project was accomplished on schedule and 30% under budget with no measurable exposure to decommissioning personnel.

Johnson, R.P.; Speed, D.L.

1985-03-15T23:59:59.000Z

35

EA-0813; Environmental Assessment and (FONSI) The Tokamak Fusion Test Reactor Decontamination and Decommissioning Project and The Tokamak Physics Experiment at the PPPL  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

13; Environmental Assessment and (FONSI) The Tokamak Fusion 13; Environmental Assessment and (FONSI) The Tokamak Fusion Test Reactor Decontamination and Decommissioning Project and The Tokamak Physics Experiment at the PPPL Table of Contents EXECUTIVE SUMMARY ACRONYMS Glossary of Radiological Terms SCIENTIFIC NOTATION 1.0 PURPOSE AND NEED FOR THE PROPOSED ACTIONS 1.1 TFTR D&D Project 1.2 TPX Project 1.3 Scope of Document 1.4 Local Community Relations Program 1.5 References 2.0 DESCRIPTION OF THE PROPOSED ACTIONS AND ALTERNATIVES 2.1 TFTR D&D Project 2.2 TPX Project 2.3 Environmental Monitoring 2.4 References 3.0 DESCRIPTION OF THE AFFECTED ENVIRONMENT 3.1 PPPL Proposed Site 3.2 ORR Alternative Site 3.3 References 4.0 ENVIRONMENTAL CONSEQUENCES OF THE PROPOSED ACTIONS AND ALTERNATIVES 4.1 TFTR D&D Project 4.1.1 Impacts of Normal D&D Operations

36

Safety of Decommissioning of Nuclear Facilities  

SciTech Connect

Full text of publication follows: ensuring safety during all stages of facility life cycle is a widely recognised responsibility of the operators, implemented under the supervision of the regulatory body and other competent authorities. As the majority of the facilities worldwide are still in operation or shutdown, there is no substantial experience in decommissioning and evaluation of safety during decommissioning in majority of Member States. The need for cooperation and exchange of experience and good practices on ensuring and evaluating safety of decommissioning was one of the outcomes of the Berlin conference in 2002. On this basis during the last three years IAEA initiated a number of international projects that can assist countries, in particular small countries with limited resources. The main IAEA international projects addressing safety during decommissioning are: (i) DeSa Project on Evaluation and Demonstration of Safety during Decommissioning; (ii) R{sup 2}D{sup 2}P project on Research Reactors Decommissioning Demonstration Project; and (iii) Project on Evaluation and Decommissioning of Former Facilities that used Radioactive Material in Iraq. This paper focuses on the DeSa Project activities on (i) development of a harmonised methodology for safety assessment for decommissioning; (ii) development of a procedure for review of safety assessments; (iii) development of recommendations on application of the graded approach to the performance and review of safety assessments; and (iv) application of the methodology and procedure to the selected real facilities with different complexities and hazard potentials (a nuclear power plant, a research reactor and a nuclear laboratory). The paper also outlines the DeSa Project outcomes and planned follow-up activities. It also summarises the main objectives and activities of the Iraq Project and introduces the R{sup 2}D{sup 2} Project, which is a subject of a complementary paper.

Batandjieva, B.; Warnecke, E.; Coates, R. [International Atomic Energy Agency, Vienna (Austria)

2008-01-15T23:59:59.000Z

37

Opportunity, risk, and success recognizing, addressing, and balancing multiple factors crucial to the success of a project management system deployed to support multi-lateral decommissioning programs  

SciTech Connect

This paper addresses the factors involved in effectively implementing a world-class program/project management information system funded by multiple nations. Along with many other benefits, investing in and utilizing such systems improves delivery and drive accountability for major expenditures. However, there are an equally large number of impediments to developing and using such systems. To be successful, the process requires a dynamic combining of elements and strategic sequencing of initiatives. While program/project-management systems involve information technologies, software and hardware, they represent only one element of the overall system.. Technology, process, people and knowledge must all be integrated and working in concert with one another to assure a fully capable system. Major system implementations occur infrequently, and frequently miss established targets in relatively small organizations (with the risk increasing with greater complexity). The European Bank of Reconstruction (EBRD) is midway through just such an implementation. The EBRD is using funds from numerous donor countries to sponsor development of an overarching program management system. The system will provide the Russian Federation with the tools to effectively manage prioritizing, planning, and physically decommissioning assets{sub i}n northwest Russia to mitigate risks associated the Soviet era nuclear submarine program. Project-management delivery using world-class techniques supported by aligned systems has been proven to increase the probability of delivering on-time and on-budget, assuring those funding such programs optimum value for money. However, systems deployed to manage multi-laterally funded projects must be developed with appropriate levels of consideration given to unique aspects such as: accommodation of existing project management methods, consideration for differences is management structures and organizational behaviors, incorporation of unique strengths, and subtle adjustment to compensate weaknesses. This paper addresses the architecture and sequencing of implementation. (authors)

Funk, Greg; Longsworth, Paul [Fluor Cumbria, Unit 8, Galemire Court, Westlakes Science Park, Moor Row, CA24 3HY (United Kingdom)

2007-07-01T23:59:59.000Z

38

Policy on Decommissioning of Department of Energy Facilities Under the  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Policy on Decommissioning of Department of Energy Facilities Under Policy on Decommissioning of Department of Energy Facilities Under the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Policy on Decommissioning of Department of Energy Facilities Under the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Purpose This Policy establishes the approach agreed upon by the Department of Energy (DOE) and Environmental Protection Agency (EPA) for the conduct of decommissioning projects [1] consistent with CERCLA requirements. This Policy creates a framework for the conduct of decommissioning of DOE facilities and provides guidance to EPA Regions and DOE Operations Offices on the use of CERCLA response authority to decommission such facilities. The principal objectives of this Policy are to ensure that decommissioning

39

Notice of Intent to Prepare an Environmental Impact Statement for Decommissioning and/or Long-Term Stewardship at the West Valley Demonstration Project and Western New York Nuclear Service Center (3/13/03)  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

4 4 Federal Register / Vol. 68, No. 49 / Thursday, March 13, 2003 / Notices Dated: March 6, 2003. Gerald A. Reynolds, Assistant Secretary for Civil Rights. [FR Doc. 03-5999 Filed 3-12-03; 8:45 am] BILLING CODE 4000-01-M DEPARTMENT OF ENERGY Notice of Intent to Prepare an Environmental Impact Statement for Decommissioning and/or Long-Term Stewardship at the West Valley Demonstration Project and Western New York Nuclear Service Center AGENCY: Department of Energy. ACTION: Notice of Intent. SUMMARY: The U.S. Department of Energy (DOE) and the New York State Energy Research and Development Authority (NYSERDA) are announcing their intent to prepare an Environmental Impact Statement (EIS) for Decommissioning and/or Long-Term Stewardship at the West Valley Demonstration Project (WVDP) and

40

3-D Model for Deactivation & Decommissioning  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Project & Identifier Project & Identifier Tech Stage: Deployment In-Situ Decommissioning: SR09171 SRS Area Closure Projects: PBS SR-0040 3-D models of the R reactor building and P reactor vessel were delivered to SRS Area Closure Projects Page 1 of 2 Tech Fact Sheet Savannah River Site South Carolina 3-D Model for Deactivation & Decommissioning Challenge Planning for the safe and controlled deactivation and decommissioning (D&D) of highly contaminated nuclear facilities requires that engineers and managers fully understand the work space in which personnel and equipment will operate. It also requires that they effectively communicate safety concerns and work sequences to the personnel who will perform the work. This crucial knowledge is conveyed in

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41

Sellafield Decommissioning Programme - Update and Lessons Learned  

SciTech Connect

The Sellafield site in North West England has over 240 active facilities covering the full nuclear cycle from fuel manufacture through generation, reprocessing and waste treatment. The Sellafield decommissioning programme was formally initiated in the mid 1980s though several plants had been decommissioned prior to this primarily to create space for other plants. Since the initiation of the programme 7 plants have been completely decommissioned, significant progress has been made in a further 16 and a total of 56 major project phases have been completed. This programme update will explain the decommissioning arrangements and strategies and illustrate the progress made on a number of the plants including the Windscale Pile Chimneys, the first reprocessing plan and plutonium plants. These present a range of different challenges and requiring approaches from fully hands on to fully remote. Some of the key lessons learned will be highlighted.

Lutwyche, P. R.; Challinor, S. F.

2003-02-24T23:59:59.000Z

42

STANDARD OPERATING PROTOCOLS FOR DECOMMISSIONING  

SciTech Connect

Decommissioning projects at Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) sites are conducted under project-specific decision documents, which involve extensive preparation time, public comment periods, and regulatory approvals. Often, the decision documents must be initiated at least one year before commencing the decommissioning project, and they are expensive and time consuming to prepare. The Rocky Flats Environmental Technology Site (RFETS) is a former nuclear weapons production plant at which hazardous substances and wastes were released or disposed during operations. As a result of the releases, RFETS was placed on the National Priorities List in 1989, and is conducting cleanup activities under a federal facilities compliance agreement. Working closely with interested stakeholders and state and federal regulatory agencies, RFETS has developed and implemented an improved process for obtaining the approvals. The key to streamlining the approval process has been the development of sitewide decision documents called Rocky Flats Cleanup Agreement Standard Operating Protocols or ''RSOPs.'' RSOPs have broad applicability, and could be used instead of project-specific documents. Although no two decommissioning projects are exactly the same and they may vary widely in contamination and other hazards, the basic steps taken for cleanup are usually similar. Because of this, using RSOPs is more efficient than preparing a separate project-specific decision documents for each cleanup action. Over the Rocky Flats cleanup life cycle, using RSOPs has the potential to: (1) Save over 5 million dollars and 6 months on the site closure schedule; (2) Eliminate preparing one hundred and twenty project-specific decision documents; and (3) Eliminate writing seventy-five closure description documents for hazardous waste unit closure and corrective actions.

Foss, D. L.; Stevens, J. L.; Gerdeman, F. W.

2002-02-25T23:59:59.000Z

43

Decommissioning Benchmarking Study Final Report  

Energy.gov (U.S. Department of Energy (DOE))

DOE's former Office of Environmental Restoration (EM-40) conducted a benchmarking study of its decommissioning program to analyze physical activities in facility decommissioning and to determine...

44

An overview of U.S. decommissioning experience -- A basic introduction  

SciTech Connect

This paper presents an overview of the US experiences in the decommissioning technical area. Sections included are: (1) an overview of the magnitude of the problem, (2) a review of the US decommissioning process, (3) regulation of decommissioning, (4) regulatory and funding requirements for decommissioning, and (5) a general overview of all on-going and completed decommissioning projects to date in the US. The final section presents a review of some issues in the decommissioning area currently being debated in the technical specialists community.

Boing, L.E.

1998-03-09T23:59:59.000Z

45

DOE Awards New York Decommissioning Services Contract | Department of  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

New York Decommissioning Services Contract New York Decommissioning Services Contract DOE Awards New York Decommissioning Services Contract June 29, 2011 - 12:00pm Addthis Media Contact Bill Taylor 513-246-0539 William.taylor@emcbc.doe.gov West Valley, NY -- The Department of Energy (DOE) today awarded a contract to CH2M Hill-B&W West Valley of Englewood, Colorado, for the Phase I Decommissioning and Facility Disposition activities at the West Valley Demonstration Project (WVDP). The contract is a performance-based, cost-plus-award-fee, completion type contract with cost and schedule incentives. The total contract value is $333.4 million. DOE has selected a phased approach for decommissioning activities at the WVDP. Phase I is the first of a two-phase process for the final decommissioning of the western New York site in accordance with the West

46

DOE Awards New York Decommissioning Services Contract | Department of  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

New York Decommissioning Services Contract New York Decommissioning Services Contract DOE Awards New York Decommissioning Services Contract June 29, 2011 - 12:00pm Addthis Media Contact Bill Taylor 513-246-0539 William.taylor@emcbc.doe.gov West Valley, NY -- The Department of Energy (DOE) today awarded a contract to CH2M Hill-B&W West Valley of Englewood, Colorado, for the Phase I Decommissioning and Facility Disposition activities at the West Valley Demonstration Project (WVDP). The contract is a performance-based, cost-plus-award-fee, completion type contract with cost and schedule incentives. The total contract value is $333.4 million. DOE has selected a phased approach for decommissioning activities at the WVDP. Phase I is the first of a two-phase process for the final decommissioning of the western New York site in accordance with the West

47

Decommissioning of the Iraq former nuclear complex  

SciTech Connect

Available in abstract form only. Full text of publication follows: A number of sites in Iraq have some degree of radiological contamination and require decommissioning and remediation in order to ensure radiological safety. Many of these sites in Iraq are located at the nuclear research centre at Al Tuwaitha. The International Atomic Energy Agency (IAEA) Board of Governors has approved a project to assist the Government of Iraq in the evaluation and decommissioning of former facilities that used radioactive materials. The project is divided into three phases: Phase 1: collect and analyze all available data and conduct training of the Iraqi staff, Phase 2: develop a decommissioning and remediation plan, and Phase 3: implement field activities relating to decommissioning, remediation and site selection suitable for final disposal of waste. Four working groups have been established to complete the Phase 1 work and significant progress has been made in drafting a new nuclear law which will provide the legal basis for the licensing of the decommissioning of the former nuclear complex. Work is also underway to collect and analysis existing date, to prioritize future activities and to develop a waste management strategy. This will be a long-term and costly project. (authors)

Abbas, Mohammed [Ministry of Science and Technology (Iraq); Helou, Tuama; Ahmead, Bushra [Ministry of Environment (Iraq); Al-Atia, Mousa; Al-Mubarak, Mowaffak [Iraqi Radiation Sources Regulatory Authority (Iraq); Danneels, Jeffrey; Cochran, John; Sorenson, Ken [Sandia National Laboratories (United States); Coates, Roger [International Atomic Energy Agency - IAEA, Wagramer Strasse 5, P.O. Box 100 - 1400 Vienna (Austria)

2007-07-01T23:59:59.000Z

48

Radiological planning and implementation for nuclear-facility decommissioning  

SciTech Connect

The need and scope of radiological planning required to support nuclear facility decommissioning are issues addressed in this paper. The role of radiation protection engineering and monitoring professionals during project implementation and closeout is also addressed. Most of the discussion focuses on worker protection considerations; however, project support, environmental protection and site release certification considerations are also covered. One objective is to identify radiological safety issues that must be addressed. The importance of the issues will vary depending on the type of facility being decommissioned; however, by giving appropriate attention to these issues difficult decommissioning projects can be accomplished in a safer manner with workers and the public receiving minimal radiation exposures.

Valentine, A.M.

1982-01-01T23:59:59.000Z

49

University of Virginia Reactor Facility Decommissioning Results  

SciTech Connect

The University of Virginia Reactor Facility started accelerated decommissioning in 2002. The facility consists of two licensed reactors, the CAVALIER and the UVAR. This paper will describe the progress in 2002, remaining efforts and the unique organizational structure of the project team.

Ervin, P. F.; Lundberg, L. A.; Benneche, P. E.; Mulder, R. U.; Steva, D. P.

2003-02-24T23:59:59.000Z

50

Systematic Approach for Decommissioning Planning and Estimating  

SciTech Connect

Nuclear facility decommissioning, satisfactorily completed at the lowest cost, relies on a systematic approach to the planning, estimating, and documenting the work. High quality information is needed to properly perform the planning and estimating. A systematic approach to collecting and maintaining the needed information is recommended using a knowledgebase system for information management. A systematic approach is also recommended to develop the decommissioning plan, cost estimate and schedule. A probabilistic project cost and schedule risk analysis is included as part of the planning process. The entire effort is performed by a experienced team of decommissioning planners, cost estimators, schedulers, and facility knowledgeable owner representatives. The plant data, work plans, cost and schedule are entered into a knowledgebase. This systematic approach has been used successfully for decommissioning planning and cost estimating for a commercial nuclear power plant. Elements of this approach have been used for numerous cost estimates and estimate reviews. The plan and estimate in the knowledgebase should be a living document, updated periodically, to support decommissioning fund provisioning, with the plan ready for use when the need arises.

Dam, A. S.

2002-02-26T23:59:59.000Z

51

A review of decommissioning considerations for new reactors  

SciTech Connect

At a time of 'nuclear renaissance' when the focus is on advanced reactor designs and construction, it is easy to overlook the decommissioning considerations because such a stage in the life of the new reactors will be some sixty years down the road. Yet, one of the lessons learned from major decommissioning projects has been that decommissioning was not given much thought when these reactors were designed three or four decades ago. Hence, the time to examine what decommissioning considerations should be taken into account is right from the design stage with regular updates of the decommissioning strategy and plans throughout the life cycle of the reactor. Designing D and D into the new reactor designs is necessary to ensure that the tail end costs of the nuclear power are manageable. Such considerations during the design stage will facilitate a more cost-effective, safe and timely decommissioning of the facility when a reactor is eventually retired. This paper examines the current regulatory and industry design guidance for the new reactors with respect to the decommissioning issues and provides a review of the design considerations that can help optimize the reactor designs for the eventual decommissioning. (authors)

Devgun, J.S.Ph.D. [Manager Nuclear Power Technologies, Sargent and Lundy LLC, Chicago, IL (United States)

2008-07-01T23:59:59.000Z

52

Nuclear Decommissioning Financing Act (Maine)  

Energy.gov (U.S. Department of Energy (DOE))

The Nuclear Decommissioning Financing Act calls for the establishment of a tax-exempt, tax-deductible decommissioning fund by the licensee of any nuclear power generating facility to pay for the...

53

Safely Decommission about how we  

E-Print Network (OSTI)

and make them available to low- income communities, individuals, and community non-profit organizations to information technologies among low-income and disadvantaged groups. #12; Safely Decommission Your PCs Learn more about how we can help you effectively decommission

Blanchette, Robert A.

54

Site decommissioning management plan  

SciTech Connect

The Nuclear Regulatory Commission (NRC) staff has identified 48 sites contaminated with radioactive material that require special attention to ensure timely decommissioning. While none of these sites represent an immediate threat to public health and safety they have contamination that exceeds existing NRC criteria for unrestricted use. All of these sites require some degree of remediation, and several involve regulatory issues that must be addressed by the Commission before they can be released for unrestricted use and the applicable licenses terminated. This report contains the NRC staff`s strategy for addressing the technical, legal, and policy issues affecting the timely decommissioning of the 48 sites and describes the status of decommissioning activities at the sites.

Fauver, D.N.; Austin, J.H.; Johnson, T.C.; Weber, M.F.; Cardile, F.P.; Martin, D.E.; Caniano, R.J.; Kinneman, J.D.

1993-10-01T23:59:59.000Z

55

Offshore decommissioning issues: Deductibility and transferability  

Science Journals Connector (OSTI)

Dealing with the decommissioning of petroleum installations is a relatively new challenge to most producer countries. It is natural to expect that industry's experience in building platforms is much greater than the one of dismantling them. Even if manifold and varied efforts are underway towards establishing international “best practices” standards in this sector, countries still enjoy rather extensive discretionary power as they practice a particular national style in the regulation of decommissioning activities in their state's jurisdiction. The present paper offers a broad panorama of this discussion, concentrating mainly on two controversial aspects. The first one analyses the ex-ante deductibility of decommissioning costs as they constitute an ex-post expense. The second discussion refers to the assignment of decommissioning responsibility in the case of transfer of exploration and production rights to new lessees during the project's life. Finally the paper applies concepts commonly used in project financing as well as structures generally used in organising pension funds to develop insights into these discussions.

Virginia Parente; Doneivan Ferreira; Edmilson Moutinho dos Santos; Estanislau Luczynski

2006-01-01T23:59:59.000Z

56

Decommissioning of the Tokamak Fusion Test Reactor  

SciTech Connect

The Tokamak Fusion Test Reactor (TFTR) at the Princeton Plasma Physics Laboratory was operated from 1982 until 1997. The last several years included operations with mixtures of deuterium and tritium. In September 2002, the three year Decontamination and Decommissioning (D&D) Project for TFTR was successfully completed. The need to deal with tritium contamination as well as activated materials led to the adaptation of many techniques from the maintenance work during TFTR operations to the D&D effort. In addition, techniques from the decommissioning of fission reactors were adapted to the D&D of TFTR and several new technologies, most notably the development of a diamond wire cutting process for complex metal structures, were developed. These techniques, along with a project management system that closely linked the field crews to the engineering staff who developed the techniques and procedures via a Work Control Center, resulted in a project that was completed safely, on time, and well below budget.

E. Perry; J. Chrzanowski; C. Gentile; R. Parsells; K. Rule; R. Strykowsky; M. Viola

2003-10-28T23:59:59.000Z

57

Stress-Assisted Corrosion in Boiler Tubes  

SciTech Connect

A number of industrial boilers, including in the pulp and paper industry, needed to replace their lower furnace tubes or decommission many recovery boilers due to stress-assisted corrosion (SAC) on the waterside of boiler tubes. More than half of the power and recovery boilers that have been inspected reveal SAC damage, which portends significant energy and economic impacts. The goal of this project was to clarify the mechanism of stress-assisted corrosion (SAC) of boiler tubes for the purpose of determining key parameters in its mitigation and control. To accomplish this in-situ strain measurements on boiler tubes were made. Boiler water environment was simulated in the laboratory and effects of water chemistry on SAC initiation and growth were evaluated in terms of industrial operations. Results from this project have shown that the dissolved oxygen is single most important factor in SAC initiation on carbon steel samples. Control of dissolved oxygen can be used to mitigate SAC in industrial boilers. Results have also shown that sharp corrosion fatigue and bulbous SAC cracks have similar mechanism but the morphology is different due to availability of oxygen during boiler shutdown conditions. Results are described in the final technical report.

Preet M Singh; Steven J Pawel

2006-05-27T23:59:59.000Z

58

Progress in Decommissioning the Humboldt Bay Power Plant - 13604  

SciTech Connect

Decommissioning of the Pacific Gas and Electric (PG and E) Company Humboldt Bay Power Plant (HBPP) Unit 3 nuclear facility has now, after more than three decades of SAFSTOR and initial decommissioning work, transitioned to full-scale decommissioning. Decommissioning activities to date have been well orchestrated and executed in spite of an extremely small work site with space constricted even more by other concurrent on-site major construction projects including the demolition of four fossil units, construction of a new generating station and 60 KV switchyard upgrade. Full-scale decommissioning activities - now transitioning from Plant Systems Removal (PG and E self-perform) to Civil Works Projects (contractor performed) - are proceeding in a safe, timely, and cost effective manner. As a result of the successful decommissioning work to date (approximately fifty percent completed) and the intense planning and preparations for the remaining work, there is a high level of confidence for completion of all HBPP Unit 3 decommissions activities in 2018. Strategic planning and preparations to transition into full-scale decommissioning was carried out in 2008 by a small, highly focused project team. This planning was conducted concurrent with other critical planning requirements such as the loading of spent nuclear fuel into dry storage at the Independent Spent Fuel Storage Installation (ISFSI) finishing December 2008. Over the past four years, 2009 through 2012, the majority of decommissioning work has been installation of site infrastructure and removal of systems and components, known as the Plant System Removal Phase, where work scope was dynamic with significant uncertainty, and it was self-performed by PG and E. As HBPP Decommissioning transitions from the Plant System Removal Phase to the Civil Works Projects Phase, where work scope is well defined, a contracting plan similar to that used for Fossil Decommissioning will be implemented. Award of five major work scopes in various stages of development are planned as they include: Turbine Building Demolition, Nuclear Facilities Demolition and Excavation, Intake and Discharge Canal Remediation, Office Facility Demobilization, and Final Site Restoration. Benefits realized by transitioning to the Civil Works Projects Phase with predominant firm fixed-price/fixed unit price contracting include single civil works contractor who can coordinate concrete shaving, liner removal, structural removal, and other demolition activities; streamline financial control; reduce PG and E overhead staffing; and provide a specialized Bidder Team with experience from other similar projects. (authors)

Rod, Kerry [PG and E Utility, Humboldt Bay Power Plant, 1000 King Salmon Ave. Eureka, CA 95503 (United States)] [PG and E Utility, Humboldt Bay Power Plant, 1000 King Salmon Ave. Eureka, CA 95503 (United States); Shelanskey, Steven K. [Anata Management Solutions, 5180 South Commerce Dr,, Suite F Murray, UT 84107 (United States)] [Anata Management Solutions, 5180 South Commerce Dr,, Suite F Murray, UT 84107 (United States); Kristofzski, John [CH2MHILL, 295 Bradley Blvd. Suite 300, Richland WA 99353 (United States)] [CH2MHILL, 295 Bradley Blvd. Suite 300, Richland WA 99353 (United States)

2013-07-01T23:59:59.000Z

59

Decommissioning Implementation Guide  

Directives, Delegations, and Requirements

The Department of Energy (DOE) faces an enormous task in the disposition of the nation's excess facilities. Many of these facilities are large and complex and contain potentially hazardous substances. As DOE facilities complete mission operations and are declared excess, they pass into a transition phase which ultimately prepares them for disposition. The disposition phase of a facility's life-cycle usually includes deactivation, decommissioning, and surveillance and maintenance (S&M) activities.

1999-09-02T23:59:59.000Z

60

DOE-EM'S In-Situ Decommissioning Strategy  

SciTech Connect

This paper addressed the current status of decommissioning projects within the Department of Energy (DOE) that have an end state of permanent entombment, referred to as in-situ decommissioning (ISD). The substance of a Department of Energy, Office of Environmental Management (DOE-EM) review of ISD and the development of a strategy are summarized. The strategy first recognizes ISD as a viable decommissioning end state; secondly addresses the integration of this approach within the external and internal regulatory regimes; subsequently identifies tools that need developing; and finally presents guidance for implementation. The overall conclusion is that ISD is a viable mode of decommissioning that can be conducted within the existing structure of rules and regulations. (author)

Negin, C.A.; Urland, C.S. [Chuck, Project Enhancement Corporation, Germantown, MD (United States); Szilagyi, A.P. [Andy, U.S. Department of Energy, Germantown, MD (United States)

2008-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "tube project decommissioning" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


61

Development of a Preliminary Decommissioning Plan Following the International Structure for Decommissioning Costing (ISDC) of Nuclear Installations - 13361  

SciTech Connect

The International Structure for Decommissioning Costing (ISDC) of Nuclear Installations, published by OECD/NEA, IAEA and EC is intended to provide a uniform list of cost items for decommissioning projects and provides a standard format that permits international cost estimates to be compared. Candesco and DECOM have used the ISDC format along with two costing codes, OMEGA and ISDCEX, developed from the ISDC by DECOM, in three projects: the development of a preliminary decommissioning plan for a multi-unit CANDU nuclear power station, updating the preliminary decommissioning cost estimates for a prototype CANDU nuclear power station and benchmarking the cost estimates for CANDU against the cost estimates for other reactor types. It was found that the ISDC format provides a well defined and transparent basis for decommissioning planning and cost estimating that assists in identifying gaps and weaknesses and facilitates the benchmarking against international experience. The use of the ISDC can also help build stakeholder confidence in the reliability of the plans and estimates and the adequacy of decommissioning funding. (authors)

Moshonas Cole, Katherine; Dinner, Julia; Grey, Mike [Candesco - A Division of Kinectrics Inc, 26 Wellington E 3rd floor, Toronto, Ontario, M5E 1S2 (Canada)] [Candesco - A Division of Kinectrics Inc, 26 Wellington E 3rd floor, Toronto, Ontario, M5E 1S2 (Canada); Daniska, Vladimir [DECOM a.s., Sibirska 1, 917 01 Trnava (Slovakia)] [DECOM a.s., Sibirska 1, 917 01 Trnava (Slovakia)

2013-07-01T23:59:59.000Z

62

Plan for decommissioning the Tokamak Fusion Test Reactor  

SciTech Connect

The Tokamak Fusion Test Reactor (TFTR) Project is in the planning phase of developing a decommissioning project. A Preliminary Decontamination and Decommissioning (D D) Plan has been developed which provides a framework for the baseline approach, and the cost and schedule estimates. TFTR will become activated and contaminated with tritium after completion of the deuterium-tritium (D-T) experiments. Hence some of the D D operations will require remote handling. It is expected that all of the waste generated will be low level radioactive waste (LLW). The objective of the D D Project is to make TFTR Test Cell available for use by a new fusion experiment. This paper discusses the D D objectives, the facility to be decommissioned, estimates of activation, the technical (baseline) approach, and the assumptions used to develop cost and schedule estimates.

Spampinato, P.T.; Walton, G.R. (Princeton Univ., NJ (United States). Plasma Physics Lab.); Commander, J.C. (EG and G Idaho, Inc., Idaho Falls, ID (United States))

1993-01-01T23:59:59.000Z

63

Plan for decommissioning the Tokamak Fusion Test Reactor  

SciTech Connect

The Tokamak Fusion Test Reactor (TFTR) Project is in the planning phase of developing a decommissioning project. A Preliminary Decontamination and Decommissioning (D&D) Plan has been developed which provides a framework for the baseline approach, and the cost and schedule estimates. TFTR will become activated and contaminated with tritium after completion of the deuterium-tritium (D-T) experiments. Hence some of the D&D operations will require remote handling. It is expected that all of the waste generated will be low level radioactive waste (LLW). The objective of the D&D Project is to make TFTR Test Cell available for use by a new fusion experiment. This paper discusses the D&D objectives, the facility to be decommissioned, estimates of activation, the technical (baseline) approach, and the assumptions used to develop cost and schedule estimates.

Spampinato, P.T.; Walton, G.R. [Princeton Univ., NJ (United States). Plasma Physics Lab.; Commander, J.C. [EG and G Idaho, Inc., Idaho Falls, ID (United States)

1993-12-31T23:59:59.000Z

64

Shippingport Station Decommissioning Project decommissioning plan. Volume II  

SciTech Connect

This volume appendix on activity specifications is divided into the following: site preparation; barge loading facility; facility closeout and restoration; preparation for removal of reactor pressure vessel, internals, and neutron shield tank package; heavy lifting and hauling; barge transportation; and Hanford transportation. (DLC)

Not Available

1983-01-01T23:59:59.000Z

65

Shippingport Station Decommissioning Project decommissioning plan. Volume 3  

SciTech Connect

Information is presented concerning the removal of both contaminated and non-contaminated piping and equipment from the Shippingport reactor.

Not Available

1983-08-01T23:59:59.000Z

66

Shippingport Station Decommissioning Project decommissioning plan. Part 2. Volume 11  

SciTech Connect

Information is presented concerning the cost-benefit analysis for decontamination of the Shippingport reactor and radiation-contamination survey data.

Not Available

1983-01-01T23:59:59.000Z

67

Shippingport Station Decommissioning Project decommissioning plan. Volume XI, Part I  

SciTech Connect

This document is divided into the following parts: radioactive waste processing, salvage/scrap value estimate, and radionuclide inventory of primary systems. (DLC)

Not Available

1983-07-01T23:59:59.000Z

68

Shippingport Station Decommissioning Project decommissioning plan. Part 2. Volume 6  

SciTech Connect

Information is presented concerning resource leveled logic report; report of remaining area work; activity specification schedules; and DOC activities.

Not Available

1983-01-01T23:59:59.000Z

69

Shippingport Station Decommissioning Project decommissioning plan. Part 2. Volume 9  

SciTech Connect

Appendices are included with information concerning DOE order 5480.1A on environmental protection and health protection; 29 CFR 1910.1001 and 40CFR61 concerning asbestos; Corps of Engineers permit information; Pennsylvania air standards; Pennsylvania water standards; Pennsylvania solid waste management; erosion control regulations; explosives regulations; and NPDES permit.

Not Available

1983-01-01T23:59:59.000Z

70

Shippingport Station Decommissioning Project decommissioning plan. Volume VI, Part II  

SciTech Connect

This document comprises the following: report of remaining contractor work, predecessor/successor logic report, contractor interface report (incoming and outgoing interfaces), and activity specification Barchart plot. (DLC)

Not Available

1984-01-01T23:59:59.000Z

71

Shippingport station decommissioning project: decommissioning plan. Volume No. 5  

SciTech Connect

The activity specifications for solid waste management, decontamination, sludge removal, decontamination of reactor coolant purification system, and systems operation support are given, together with supplementary requirements for welding and work breakdown structure dictionary. (DLC)

Not Available

1983-08-01T23:59:59.000Z

72

Shipppingport Station Decommissioning Project decommissioning plan. Volume 10  

SciTech Connect

Appendices are presented concerning activation analysis; reactor and intervals removal; reactor vessel removal; escalation effects; removal of contaminated concrete; and removal of contaminated chanbers.

Not Available

1983-01-01T23:59:59.000Z

73

Guides: Design/Engineering for Deactivation & Decommissioning | Department  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Guides: Design/Engineering for Deactivation & Guides: Design/Engineering for Deactivation & Decommissioning Guides: Design/Engineering for Deactivation & Decommissioning To ensure development of appropriate levels of engineering detail, DOE-EM's Office of Deactivation and Decommissioning and Facility Engineering (EM-13) has prepared this guidance for tailoring a D&D project's engineering/design to meet the objectives of the CD milestones. The enhanced rigor in planning and systematic, forward looking approach to engineering/design recommended in this guidance is intended to ensure that the level of detail in technical planning and technical development, integrated with other project aspects such as safety basis modifications, leads to a high confidence that the engineered system as a whole will function as designed. As the level of

74

NETL F 451.1-1/1 Categorical Exclusion (CX) Designation Form  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

DOENETL FE 0513 ORD 2011 John Ontko Approx. one month NETL: Morgantown, WV Vortex Tube Project Decommissioning Project Decommissioning of Vortex Tube project located in Buildings...

75

Apparatus Drawings Project. Report Number 17. Small X-Ray Tube  

Science Journals Connector (OSTI)

A small well-shielded high-vacuum molybdenum-anode x-ray tube designed for use as an ionizing source with a Millikan oil-drop apparatus is described. An accelerating potential of 28-kv peak provides a continuous x-ray spectrum with a short-wavelength cutoff of 0.436 A as well as the intense K L M and N series of the characteristic line spectrum of molybdenum. The 28-kv accelerating potential with a saturation current of 0.2–0.3 ma rms ensures adequate ionization with conventional equipment while still permitting the convenient installation of the massive external shielding necessary in a teaching laboratory. Information on essential safety precautions and construction procedures is given.

Robert G. Marcley

1961-01-01T23:59:59.000Z

76

Decontamination & decommissioning focus area  

SciTech Connect

In January 1994, the US Department of Energy Office of Environmental Management (DOE EM) formally introduced its new approach to managing DOE`s environmental research and technology development activities. The goal of the new approach is to conduct research and development in critical areas of interest to DOE, utilizing the best talent in the Department and in the national science community. To facilitate this solutions-oriented approach, the Office of Science and Technology (EM-50, formerly the Office of Technology Development) formed five Focus AReas to stimulate the required basic research, development, and demonstration efforts to seek new, innovative cleanup methods. In February 1995, EM-50 selected the DOE Morgantown Energy Technology Center (METC) to lead implementation of one of these Focus Areas: the Decontamination and Decommissioning (D & D) Focus Area.

NONE

1996-08-01T23:59:59.000Z

77

decommissioning of carbon dioxide (CO  

NLE Websites -- All DOE Office Websites (Extended Search)

decommissioning of carbon dioxide (CO decommissioning of carbon dioxide (CO 2 ) storage wells. The manual builds on lessons learned through NETL research; the experiences of the Regional Carbon Sequestration Partnerships' (RCSPs) carbon capture, utilization, and storage (CCUS) field tests; and the acquired knowledge of industries that have been actively drilling wells for more than 100 years. In addition, the BPM provides an overview of the well-

78

Capturing Process Knowledge for Facility Deactivation and Decommissioning  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Tech Assistance Tech Assistance Savannah River National Laboratory- Assess Adequacy of Process Knowledge for D&D Guidance for Determining Adequacy of Process Knowledge Page 1 of 2 Savannah River National Laboratory South Carolina Capturing Process Knowledge for Facility Deactivation and Decommissioning Challenge The Office of Environmental Management (EM) is responsible for the disposition of a vast number of facilities at numerous sites around the country which have been declared excess to current mission needs. When such excess facilities are scheduled for deactivation and decommissioning (D&D), among the tasks the responsible project team is faced with include the evaluation and planning for the removal, characterization, and disposition of all legacy

79

Status of the NRC Decommissioning Program  

SciTech Connect

On July 21, 1997, the U.S. Nuclear Regulatory Commission (NRC) published the final rule on Radiological Criteria for License Termination (the License Termination Rule or LTR) as Subpart E to 10 CFR Part 20. NRC regulations require that materials licensees submit Decommissioning Plans to support the decommissioning of its facility if it is required by license condition, or if the procedures and activities necessary to carry out the decommissioning have not been approved by NRC and these procedures could increase the potential health and safety impacts to the workers or the public. NRC regulations also require that reactor licensees submit Post-shutdown Decommissioning Activities Reports and License Termination Plans to support the decommissioning of nuclear power facilities. This paper provides an update on the status of the NRC's decommissioning program that was presented during WM'02. It discusses the staff's current efforts to streamline the decommissioning process, current issues being faced in the decommissioning program, such as partial site release and restricted release of sites, as well as the status of the decommissioning of complex sites and those listed in the Site Decommissioning Management Plan. The paper discusses the status of permanently shut-down commercial power reactors and the transfer of complex decommissioning sites and sites listed on the SDMP to Agreement States. Finally the paper provides an update of the status of various tools and guidance the NRC is developing to assist licensees during decommissioning, including an effort to consolidate and risk-inform decommissioning guidance.

Orlando, D. A.; Camper, L.; Buckley, J.; Pogue, E.; Banovac, K.

2003-02-24T23:59:59.000Z

80

Is Entombment an Acceptable Option for Decommissioning? An International Perspective - 13488  

SciTech Connect

Selection of a decommissioning strategy is one of the key steps in the preparation for decommissioning of nuclear facilities and other facilities using radioactive material. Approaches being implemented or considered by Member States include immediate dismantling, deferred dismantling and entombment. Other options or slight modifications of these strategies are also possible. Entombment has been identified in the current International Atomic Energy Agency (IAEA) Safety Standards as one of the three basic decommissioning strategies and has been defined as a decommissioning strategy by which radioactive contaminants are encased in a structurally long lived material until radioactivity decays to a level permitting the unrestricted release of the facility, or release with restrictions imposed by the regulatory body. Although all three strategies have been considered, in principle, applicable to all facilities, their application to some facilities may not be appropriate owing to political concerns, safety or environmental requirements, technical considerations, local conditions or financial considerations. The IAEA is currently revising the decommissioning Safety Standards and one of the issues widely discussed has been the applicability of entombment in the context of decommissioning and its general objective to enable removal of regulatory control from the decommissioned facility. The IAEA recently established a consultancy to collect and discuss experience and lessons learned from entombment projects, to identify regulatory requirements and expectations for applying entombment as a decommissioning option strategy, in compliance with the internationally agreed standards. (authors)

Belencan, Helen [US Department of Energy (United States)] [US Department of Energy (United States); Nys, Vincent [Federal Agency for Nuclear Control (Belgium)] [Federal Agency for Nuclear Control (Belgium); Guskov, Andrey [Scientific and Engineering Centre on Safety in Nuclear Energy (United States)] [Scientific and Engineering Centre on Safety in Nuclear Energy (United States); Francois, Patrice [Institut de radioprotection et de surete nucleaire (France)] [Institut de radioprotection et de surete nucleaire (France); Watson, Bruce [US Nuclear Regulatory Commission (United States)] [US Nuclear Regulatory Commission (United States); Ljubenov, Vladan [International Atomic Energy Agency (Austria)] [International Atomic Energy Agency (Austria)

2013-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "tube project decommissioning" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


81

Decontamination and decommissioning of 61 plutonium gloveboxes in D-Wing, Building 212 Argonne National Laboratory-East: Final project report  

SciTech Connect

Argonne National Laboratory-East (ANL-E) is a government-owned, contractor operated, multipurpose research facility located 25 miles southwest of downtown Chicago on 689 hectares (1,700 acres) in DuPage County, Illinois, as shown in Figure 1.1. Building 212 is located in the central area of ANL-E, as shown in Figure 1.2. The purpose of this project was to eliminate the risk of radioactive material release from the contaminated glovebox systems and to make the laboratories available for unrestricted use. The following work objectives were established: (1) Identify and remove radioactive materials for return to ANL-E Special Materials control. (2) Remove and package the radioactively contaminated materials and equipment from the gloveboxes. (3) Decontaminate the gloveboxes to nontransuranic (non-TRU) levels. (4) Size-reduce and package the gloveboxes and support systems. (5) Document and dispose of the radioactive and mixed waste. (6) Decontaminate, survey, and release the nine laboratories and corridor areas for unrestricted use.

Cheever, C.L.; Rose, R.W.

1996-09-01T23:59:59.000Z

82

EIS-0226: Decommissioning and/or Long-Term Stewardship at the West Valley  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

26: Decommissioning and/or Long-Term Stewardship at the West 26: Decommissioning and/or Long-Term Stewardship at the West Valley Demonstration Project and Western New York Nuclear Service Center EIS-0226: Decommissioning and/or Long-Term Stewardship at the West Valley Demonstration Project and Western New York Nuclear Service Center SUMMARY This EIS evaluates the potential environmental impacts of the range of reasonable alternatives to decommission and/or maintain long-term stewardship at WNYNSC. The alternatives analyzed in the EIS include the Sitewide Removal Alternative, the Sitewide Close-In-Place Alternative, the Phased Decisionmaking Alternative (Preferred Alternative), and the No Action Alternative. The analysis and information contained in the EIS are intended to assist DOE and NYSERDA with the consideration of environmental

83

IMPACTS OF INTERACTING ELEVATED ATMOSPHERIC CO2 AND O3 ON THE STRUCTURE AND FUNCTIONING OF A NORTHERN FOREST ECOSYSTEM: OPERATING AND DECOMMISSIONING THE ASPEN FACE PROJECT  

SciTech Connect

Two of the most important and pervasive greenhouse gases driving global change and impacting forests in the U.S. and around the world are atmospheric CO2 and tropospheric O3. As the only free air, large-scale manipulative experiment studying the interaction of elevated CO2 and O3 on forests, the Aspen FACE experiment was uniquely designed to address the long-term ecosystem level impacts of these two greenhouse gases on aspen-birch-maple forests, which dominate the richly forested Lake States region. The project was established in 1997 to address the overarching scientific question: “What are the effects of elevated [CO2] and [O3], alone and in combination, on the structure and functioning of northern hardwood forest ecosystems?” From 1998 through the middle of the 2009 growing season, we examined the interacting effects of elevated CO2 and O3 on ecosystem processes in an aggrading northern forest ecosystem to compare the responses of early-successional, rapid-growing shade intolerant trembling aspen and paper birch to those of a late successional, slower growing shade tolerant sugar maple. Fumigations with elevated CO2 (560 ppm during daylight hours) and O3 (approximately 1.5 x ambient) were conducted during the growing season from 1998 to 2008, and in 2009 through harvest date. Response variables quantified during the experiment included growth, competitive interactions and stand dynamics, physiological processes, plant nutrient status and uptake, tissue biochemistry, litter quality and decomposition rates, hydrology, soil respiration, microbial community composition and respiration, VOC production, treatment-pest interactions, and treatment-phenology interactions. In 2009, we conducted a detailed harvest of the site. The harvest included detailed sampling of a subset of trees by component (leaves and buds, fine branches, coarse branches and stem, coarse roots, fine roots) and excavation of soil to a depth of 1 m. Throughout the experiment, aspen and birch photosynthesis increased with elevated CO2 and tended to decrease with elevated O3, compared to the control. In contrast to aspen and birch, maple photosynthesis was not enhanced by elevated CO2. Elevated O3 did not cause significant reductions in maximum photosynthesis in birch or maple. In addition, photosynthesis in ozone sensitive clones was affected to a much greater degree than that in ozone tolerant aspen clones. Treatment effects on photosynthesis contributed to CO2 stimulation of aboveground and belowground growth that was species and genotype dependent, with birch and aspen being most responsive and maple being least responsive. The positive effects of elevated CO2 on net primary productivity NPP were sustained through the end of the experiment, but negative effects of elevated O3 on NPP had dissipated during the final three years of treatments. The declining response to O3 over time resulted from the compensatory growth of O3-tolerant genotypes and species as the growth of O3-sensitive individuals declined over time. Cumulative NPP over the entire experiment was 39% greater under elevated CO2 and 10% lower under elevated O3. Enhanced NPP under elevated CO2 was sustained by greater root exploration of soil for growth-limiting N, as well as more rapid rates of litter decomposition and microbial N release during decay. Results from Aspen FACE clearly indicate that plants growing under elevated carbon dioxide, regardless of community type or ozone level, obtained significantly greater amounts of soil N. These results indicate that greater plant growth under elevated carbon dioxide has not led to “progressive N limitation”. If similar forests growing throughout northeastern North America respond in the same manner, then enhanced forest NPP under elevated CO2 may be sustained for a longer duration than previously thought, and the negative effect of elevated O3 may be diminished by compensatory growth of O3-tolerant plants as they begin to dominate forest communities. By the end of the experiment, elevated CO2 increased ecosystem C content by 11%, whereas

Burton, Andrew J. [Michigan Technological University; Zak, Donald R. [University of Michigan; Kubiske, Mark E. [USDA Forest Service; Pregitzer, Kurt S. [University of Idaho

2014-06-30T23:59:59.000Z

84

STATUS OF THE NRC'S DECOMMISSIONING PROGRAM  

SciTech Connect

On July 21, 1997, the U.S. Nuclear Regulatory Commission published the final rule on Radiological Criteria for License Termination (the License Termination Rule) as Subpart E to 10 CFR Part 20. NRC regulations require that materials licensees submit Decommissioning Plans to support the decommissioning of its facility if it is required by license condition, or if the procedures and activities necessary to carry out the decommissioning have not been approved by NRC and these procedures could increase the potential health and safety impacts to the workers or the public. NRC regulations also require that reactor licensees submit Post-shutdown Decommissioning Activities Reports and License Termination Plans to support the decommissioning of nuclear power facilities. This paper provides an update on the status of the NRC's decommissioning program. It discusses the status of permanently shut-down commercial power reactors, complex decommissioning sites, and sites listed in the Site Decommissioning Management Plan. The paper provides the status of various tools and guidance the NRC is developing to assist licensees during decommissioning, including a Standard Review Plan for evaluating plans and information submitted by licensees to support the decommissioning of nuclear facilities and the D and D Screen software for determining the potential doses from residual radioactivity. Finally, it discusses the status of the staff's current efforts to streamline the decommissioning process.

Orlando, D. A.; Camper, L. W.; Buckley, J.

2002-02-25T23:59:59.000Z

85

Decontamination & Decommissioning/ Facilities Engineering (D&D/FE) |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Decontamination & Decommissioning/ Facilities Engineering (D&D/FE) Decontamination & Decommissioning/ Facilities Engineering (D&D/FE) Decontamination & Decommissioning/ Facilities Engineering (D&D/FE) Decontamination & Decommissioning/ Facilities Engineering (D&D/FE) Decontamination & Decommissioning/ Facilities Engineering (D&D/FE) Decontamination & Decommissioning/ Facilities Engineering (D&D/FE) Decontamination & Decommissioning/ Facilities Engineering (D&D/FE) As the DOE complex sites prepare for closure, a large number of buildings and facilities must be deactivated and decommissioned. These facilities contain many complex systems (e.g. ventilation), miles of contaminated pipelines, glove boxes, and unique processing equipment that require labor intensive deactivation and decommissioning methods. Although

86

Radiochemistry Lab Decommissioning and Dismantlement. AECL, Chalk River Labs, Ontario, Canada  

SciTech Connect

Atomic Energy of Canada (AECL) was originally founded in the mid 1940's to perform research in radiation and nuclear areas under the Canadian Defense Department. In the mid 50's The Canadian government embarked on several research and development programs for the development of the Candu Reactor. AECL was initially built as a temporary site and is now faced with many redundant buildings. Prior to 2004 small amounts of Decommissioning work was in progress. Many reasons for deferring decommissioning activities were used with the predominant ones being: 1. Reduction in radiation doses to workers during the final dismantlement, 2. Development of a long-term solution for the management of radioactive wastes in Canada, 3. Financial constraints presented by the number of facilities shutdown that would require decommissioning funds and the absence of an approved funding strategy. This has led to the development of a comprehensive decommissioning plan that is all inclusive of AECL's current and legacy liabilities. Canada does not have a long-term disposal site; therefore waste minimization becomes the driving factor behind decontamination for decommissioning before and during dismantlement. This decommissioning job was a great learning experience for decommissioning and the associated contractors who worked on this project. Throughout the life of the project there was a constant focus on waste minimization. This focus was constantly in conflict with regulatory compliance primarily with respect to fire regulations and protecting the facility along with adjacent facilities during the decommissioning activities. Discrepancies in historical documents forced the project to treat every space as a contaminated space until proven differently. Decommissioning and dismantlement within an operating site adds to the complexity of the tasks especially when it is being conducted in the heart of the plant. This project was very successful with no lost time accidents in over one hundred thousand hours worked, on schedule and under budget despite some significant changes throughout the decommissioning phases. The actual cost to decommission this building will come in under 9 million dollars vs. an estimated 14.5 million dollars. This paper will cover some of the unique aspects of dismantling a radioactive building that has seen pretty much every element of the periodic table pass through it with the client requirement focused on minimization of radioactive waste volumes.

Kenny, Stephen [Acting Director of Waste Management and Decommissioning Operations, AECL, Chalk River Labs, Chalk River, Ont. (Canada)

2008-01-15T23:59:59.000Z

87

Decontamination and decommissioning of building 889 at Rocky Flats Environmental Technology Site  

SciTech Connect

At the Rocky Flats site, the building 889 decommissioning project was the first large-scale decommissioning project of a radiologically contaminated facility at Rocky Flats. The scope consisted of removal of all equipment and utility systems from the interior of the building, decontamination of interior building surfaces, and the demolition of the facility to ground level. Details of the project management plan, including schedule, engineering, cost, characterization methodologies, decontamination techniques, radiological control requirements, and demolition methods, are provided in this article. 1 fig., 3 tabs.

Dorr, K.A. [Kaiser-Hill Co., Golden, CO (United States); Hickman, M.E.; Henderson, B.J. [Rocky Mountain Remediation Services, Golden, CO (United States); Sexton, R.J. [Scientific Ecology Group, Golden, CO (United States)

1997-09-01T23:59:59.000Z

88

Decontamination, decommissioning, and vendor advertorial issue, 2005  

SciTech Connect

The focus of the July-August issue is on Decontamination, decommissioning, and vendor advertorials. Major interviews, articles and reports in this issue include: Increasing momentum, by Gary Taylor, Entergy Nuclear, Inc.; An acceptable investment, by Tom Chrisopher, Areva, Inc.; Fuel recycling for the U.S. and abroad, by Philippe Knoche, Areva, France; We're bullish on nuclear power, by Dan R. Keuter, Entergy Nuclear, Inc.; Ten key actions for decommissioning, by Lawrence E. Boing, Argonne National Laboratory; Safe, efficient and cost-effective decommissioning, by Dr. Claudio Pescatore and Torsten Eng, OECD Nuclear Energy Agency (NEA), France; and, Plant profile: SONGS decommissioning.

Agnihotri, Newal (ed.)

2005-07-15T23:59:59.000Z

89

Hallam, Nebraska, Decommissioned Reactor Site Fact Sheet  

Office of Legacy Management (LM)

Program. Objectives for the reactor were fulfilled by 1966, and the Nebraska Public Power District decommissioned and dismantled the facility between 1967 and 1969. Facility...

90

Mobile workstation for decontamination and decommissioning operations  

SciTech Connect

This project is an interdisciplinary effort to develop effective mobile worksystems for decontamination and decommissioning (D&D) of facilities within the DOE Nuclear Weapons Complex. These mobile worksystems will be configured to operate within the environmental and logistical constraints of such facilities and to perform a number of work tasks. Our program is designed to produce a mobile worksystem with capabilities and features that are matched to the particular needs of D&D work by evolving the design through a series of technological developments, performance tests and evaluations. The project has three phases. In this the first phase, an existing teleoperated worksystem, the Remote Work Vehicle (developed for use in the Three Mile Island Unit 2 Reactor Building basement), was enhanced for telerobotic performance of several D&D operations. Its ability to perform these operations was then assessed through a series of tests in a mockup facility that contained generic structures and equipment similar to those that D&D work machines will encounter in DOE facilities. Building upon the knowledge gained through those tests and evaluations, a next generation mobile worksystem, the RWV II, and a more advanced controller will be designed, integrated and tested in the second phase, which is scheduled for completion in January 1995. The third phase of the project will involve testing of the RWV II in the real DOE facility.

Whittaker, W.L.; Osborn, J.F.; Thompson, B.R. [Carnegie-Mellon Univ., Pittsburgh, PA (United States). Robotics Inst.

1993-10-01T23:59:59.000Z

91

Deactivation & Decommissioning (D&D) | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Deactivation & Deactivation & Decommissioning (D&D) Deactivation & Decommissioning (D&D) American Recovery and Reinvestment Act workers at the Savannah River Site imploded the 455-foot-tall K Reactor Cooling Tower in May 2010. The project was completed safely and contributed 36.5 square miles to the site's total footprint reduction. On August 3, 2013, contractors and the Oak Ridge Office of Environmental Management successfully completed the explosive demolition of the K-1206-F Fire Water Tower, which for 54 years had been used for fire water supply at the East Tennessee Technology Park in Oak Ridge Tennessee. The 382 foot tall, 400,000-gallon water tower tank was drained and isolated from the fire water system prior to the estimated 100-ton steel structure being

92

Decontamination and Decommissioning activities photobriefing book FY 1997  

SciTech Connect

The Decontamination and Decommissioning (D and D) Program at Argonne National Laboratory-East (ANL-E) is dedicated to the safe and cost effective D{ampersand}D of surplus nuclear facilities. There is currently a backlog of more than 7,000 contaminated US Department of Energy facilities nationwide. Added to this are 110 licensed commercial nuclear power reactors operated by utilities learning to cope with deregulation and an aging infrastructure that supports the commercial nuclear power industry, as well as medical and other uses of radioactive materials. With this volume it becomes easy to understand the importance of addressing the unique issues and objectives associated with the D{ampersand}D of surplus nuclear facilities. This photobriefing book summarizes the decontamination and decommissioning projects and activities either completed or continuing at the ANL-E site during the year.

NONE

1998-04-01T23:59:59.000Z

93

Joint US/Russian study on the development of a decommissioning strategy plan for RBMK-1000 unit No. 1 at the Leningrad Nuclear Power Plant  

SciTech Connect

The objective of this joint U.S./Russian study was to develop a safe, technically feasible, economically acceptable strategy for decommissioning Leningrad Nuclear Power Plant (LNPP) Unit No. 1 as a representative first-generation RBMK-1000 reactor. The ultimate goal in developing the decommissioning strategy was to select the most suitable decommissioning alternative and end state, taking into account the socioeconomic conditions, the regulatory environment, and decommissioning experience in Russia. This study was performed by a group of Russian and American experts led by Kurchatov Institute for the Russian efforts and by the Pacific Northwest National Laboratory for the U.S. efforts and for the overall project.

NONE

1997-12-01T23:59:59.000Z

94

Rancho Seco--Decommissioning Update  

SciTech Connect

The Rancho Seco Nuclear Generating Station ceased operation in June of 1989 and entered an extended period of SAFSTOR to allow funds to accumulate for dismantlement. Incremental dismantlement was begun in 1997 of steam systems and based on the successful completion of work, the Sacramento Municipal Utility District (SMUD) board of directors approved full decommissioning in July 1999. A schedule has been developed for completion of decommissioning by 2008, allowing decommissioning funds to accumulate until they are needed. Systems removal began in the Auxiliary Building in October of 1999 and in the Reactor Building in January of 2000. Systems dismantlement continues in the Reactor Building and should be completed by the end of 2003. System removal is near completion in the Auxiliary Building with removal of the final liquid waste tanks in progress. The spent fuel has been moved to dry storage in an onsite ISFSI, with completion on August 21, 2002. The spent fuel racks are currently being removed from the pool, packaged and shipped, and then the pool will be cleaned. Also in the last year the reactor coolant pumps and primary piping were removed and shipped. Characterization and planning work for the reactor vessel and internals is also in progress with various cut-up and/or disposal options being evaluated. In the year ahead the remaining systems in the Reactor Building will be removed, packaged and sent for disposal, including the pressurizer. Work will be started on embedded and underground piping and the large outdoor tanks. Building survey and decontamination will begin. RFP's for removal of the vessel and internals and the steam generators are planned to fix the cost of those components. If the costs are consistent with current estimates the work will go forward. If they are not, hardened SAFSTOR/entombment may be considered.

Newey, J. M.; Ronningen, E. T.; Snyder, M. W.

2003-02-26T23:59:59.000Z

95

Waste Management Strategy for Dismantling Waste to Reduce Costs for Power Plant Decommissioning - 13543  

SciTech Connect

Decommissioning of nuclear power plants generates large volumes of radioactive or potentially radioactive waste. The proper management of the dismantling waste plays an important role for the time needed for the dismantling phase and thus is critical to the decommissioning cost. An efficient and thorough process for inventorying, characterization and categorization of the waste provides a sound basis for the planning process. As part of comprehensive decommissioning studies for Nordic NPPs, Westinghouse has developed the decommissioning inventories that have been used for estimations of the duration of specific work packages and the corresponding costs. As part of creating the design basis for a national repository for decommissioning waste, the total production of different categories of waste packages has also been predicted. Studsvik has developed a risk based concept for categorization and handling of the generated waste using six different categories with a span from extremely small risk for radiological contamination to high level waste. The two companies have recently joined their skills in the area of decommissioning on selected market in a consortium named 'ndcon' to further strengthen the proposed process. Depending on the risk for radiological contamination or the radiological properties and other properties of importance for waste management, treatment routes are proposed with well-defined and proven methods for on-site or off-site treatment, activity determination and conditioning. The system is based on a graded approach philosophy aiming for high confidence and sustainability, aiming for re-use and recycling where found applicable. The objective is to establish a process where all dismantled material has a pre-determined treatment route. These routes should through measurements, categorization, treatment, conditioning, intermediate storage and final disposal be designed to provide a steady, un-disturbed flow of material to avoid interruptions. Bottle-necks in the process causes increased space requirements and will have negative impact on the project schedule, which increases not only the cost but also the dose exposure to personnel. For these reasons it is critical to create a process that transfers material into conditioned waste ready for disposal as quickly as possible. To a certain extent the decommissioning program should be led by the waste management process. With the objective to reduce time for handling of dismantled material at site and to efficiently and environmental-friendly use waste management methods (clearance for re-use followed by clearance for recycling), the costs for the plant decommissioning could be reduced as well as time needed for performing the decommissioning project. Also, risks for delays would be reduced with a well-defined handling scheme which limits surprises. Delays are a major cost driver for decommissioning projects. (authors)

Larsson, Arne; Lidar, Per [Studsvik Nuclear AB, SE-611 82 Nykoeping (Sweden)] [Studsvik Nuclear AB, SE-611 82 Nykoeping (Sweden); Bergh, Niklas; Hedin, Gunnar [Westinghouse Electric Sweden AB, Fredholmsgatan 2, SE-721 63, Vaesteraas (Sweden)] [Westinghouse Electric Sweden AB, Fredholmsgatan 2, SE-721 63, Vaesteraas (Sweden)

2013-07-01T23:59:59.000Z

96

In-Situ Decommissioning | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Site & Facility Restoration » Deactivation & Site & Facility Restoration » Deactivation & Decommissioning (D&D) » In-Situ Decommissioning In-Situ Decommissioning In-Situ Decommissioning (ISD) is the permanent entombment of a facility that contains residual radiological and/or chemical contamination. The ISD approach is a cost-effective alternative to both demolition and complete removal of the structure and its content (including the cost of transport and disposal). In addition, the effective use of ISD reduces human health and safety risks while helping to attain sustainability goals through the reduction of greenhouse gas (GHG) emissions, petroleum consumption and waste generation. Not all contaminated structures can be decommissioned using ISD; canditate sites must meet strict criteria.

97

Decommissioning Cost Estimating Factors And Earned Value Integration  

SciTech Connect

The Rocky Flats 771 Project progressed from the planning stage of decommissioning a plutonium facility, through the strip-out of highly-contaminated equipment, removal of utilities and structural decontamination, and building demolition. Actual cost data was collected from the strip-out activities and compared to original estimates, allowing the development of cost by equipment groupings and types and over time. Separate data was developed from the project control earned value reporting and compared with the equipment data. The paper discusses the analysis to develop the detailed factors for the different equipment types, and the items that need to be considered during characterization of a similar facility when preparing an estimate. The factors are presented based on direct labor requirements by equipment type. The paper also includes actual support costs, and examples of fixed or one-time start-up costs. The integration of the estimate and the earned value system used for the 771 Project is also discussed. The paper covers the development of the earned value system as well as its application to a facility to be decommissioned and an existing work breakdown structure. Lessons learned are provided, including integration with scheduling and craft supervision, measurement approaches, and verification of scope completion. In summary: The work of decommissioning the Rocky Flats 771 Project process equipment was completed in 2003. Early in the planning process, we had difficulty in identifying credible data and implementing processes for estimating and controlling this work. As the project progressed, we were able to collect actual data on the costs of removing plutonium contaminated equipment from various areas over the life of this work and associate those costs with individual pieces of equipment. We also were able to develop and test out a system for measuring the earned value of a decommissioning project based on an evolving estimate. These were elements that would have been useful to us in our early planning process, and we would expect that they would find application elsewhere as the DOE weapons complex and some commercial nuclear facilities move towards closure. (authors)

Sanford, P.C.; Cimmarron, E. [Englewood, CO, B. Skokan, Office of Project Management Oversight, EM-53, United States Department of Energy, Washington, DC (United States)

2008-07-01T23:59:59.000Z

98

FY 2000 Deactivation and Decommissioning Focus Area Annual Report  

SciTech Connect

This document describes activities of the Deactivation and Decommissioning Focus Area for the past year.

None

2001-03-01T23:59:59.000Z

99

Guides: Design/Engineering for Deactivation & Decommissioning  

Energy.gov (U.S. Department of Energy (DOE))

To ensure development of appropriate levels of engineering detail, DOE-EM’s Office of Deactivation and Decommissioning and Facility Engineering (EM-13) has prepared this guidance for  tailoring a D...

100

ECONOMIC MODELING OF RE-LICENSING AND DECOMMISSIONING OPTIONS FOR THE  

E-Print Network (OSTI)

ECONOMIC MODELING OF RE-LICENSING AND DECOMMISSIONING OPTIONS FOR THE KLAMATH BASIN HYDROELECTRIC, and steelhead trout on the West Coast of the United States. PacifiCorp's 169-megawatt Klamath Hydroelectric Hydroelectric Project is the only thorough, objective and transparent assessment tool that analyzes the cost

Note: This page contains sample records for the topic "tube project decommissioning" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


101

Decommissioning of TA-21-153, a /sup 227/Ac contaminated old filter building  

SciTech Connect

An exhaust air filter building contaminated with /sup 227/Ac was decommissioned at the Los Alamos National Laboratory, Los Alamos, New Mexico, in 1978. The building was constructed in the late 1940s to clean exhaust air from several buildings at TA-21, DP Site. It was in service until March 1970. The project involved preliminary decontamination, dismantling the building, and burying the debris at an on-site waste disposal/storage area. This report presents the details on the decommissioning procedures, health physics, waste management, environmental surveillance, and costs for the operation.

Harper, J.R.; Garde, R.

1981-11-01T23:59:59.000Z

102

DECOMMISSIONING OF THE NUCLEAR FACILITIES OF VKTA AT THE ROSSENDORF RESEARCH SITE  

SciTech Connect

VKTA decommissioned the old nuclear facilities of former GDR's (German Democratic Republic) Central Institute of Nuclear Research which was closed end of 1991. VKTA is responsible for fissile material and waste management, environmental and radiation protection and runs an accredited laboratory for environmental and radionuclide analytics. The Rossendorf research site is located east of the city of Dresden. The period from 1982 to about 1997 was mainly characterized by obtaining the necessary licenses for decommissioning and developing a new infrastructure (i.e. waste treatment facility, interim storages for fissile material and waste, clearance monitoring facility). The decommissioning work has been in progress since that time. The decommissioning projects are concentrated on three complexes: (1) the reactors and a fuel development and testing facility, (2) the radioisotope production facilities, and (3) the former liquid and solid waste storage facilities. The status of decommissioning progress and treatment of the residues will be demonstrated. Finally an outlook will be given on the future tasks of VKTA based on the ''Conception VKTA 2000 plus'', which was confirmed by the Saxonian government last year.

U. Helwig, W. Boessert

2003-02-27T23:59:59.000Z

103

DOE EM Project Experience & Lessons Learned for In Situ Decommissionin...  

Office of Environmental Management (EM)

"DOE EM Project Experience & Lessons Learned for In Situ Decommissioning" report is to capture the considerable technical experience gained to date for implementation of In Situ...

104

Deactivation & Decommissioning (D&D) Program Map | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Services » Site & Facility Restoration » Deactivation & Services » Site & Facility Restoration » Deactivation & Decommissioning (D&D) » Deactivation & Decommissioning (D&D) Program Map Deactivation & Decommissioning (D&D) Program Map Above on the left is K-25, at Oak Ridge before and after the 844,000 sq-ft demolition. In addition, on the right: K Cooling Tower at Savannah River Site demolition. Above on the left is K-25, at Oak Ridge before and after the 844,000 sq-ft demolition. In addition, on the right: K Cooling Tower at Savannah River Site demolition. The "D&D Program Map" presents an integrated overview of DOE's complex-wide D&D project locations, scope, and issues and includes information on: * The affects of the AMERICAN Recovery and Reinvestment Act of 2009

105

Deactivation & Decommissioning (D&D) Program Map | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Services » Site & Facility Restoration » Deactivation & Services » Site & Facility Restoration » Deactivation & Decommissioning (D&D) » Deactivation & Decommissioning (D&D) Program Map Deactivation & Decommissioning (D&D) Program Map Above on the left is K-25, at Oak Ridge before and after the 844,000 sq-ft demolition. In addition, on the right: K Cooling Tower at Savannah River Site demolition. Above on the left is K-25, at Oak Ridge before and after the 844,000 sq-ft demolition. In addition, on the right: K Cooling Tower at Savannah River Site demolition. The "D&D Program Map" presents an integrated overview of DOE's complex-wide D&D project locations, scope, and issues and includes information on: * The affects of the AMERICAN Recovery and Reinvestment Act of 2009

106

Confidentiality Agreement between the Nuclear Decommissioning Authority and  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Services » Communication & Engagement » International Programs » Services » Communication & Engagement » International Programs » Confidentiality Agreement between the Nuclear Decommissioning Authority and US Department of Energy Confidentiality Agreement between the Nuclear Decommissioning Authority and US Department of Energy Confidentiality Agreement between the Nuclear Decommissioning Authority in UK and US Department of Energy Confidentiality Agreement between the Nuclear Decommissioning Authority and US Department of Energy More Documents & Publications Statement of Intent between the US Department of Energy and UK Nuclear Decommissioning Authority Scanned_Agreement.pdf Statement of Intent NO. 2 between the US Department of Energy and UK Nuclear Decommissioning Authority Waste Management Nuclear Materials & Waste

107

Decommissioning Under CERCLA Information Sheet | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Decommissioning Under CERCLA Information Sheet Decommissioning Under CERCLA Information Sheet Decommissioning Under CERCLA Information Sheet This Question and Answer (Q&A) Sheet discusses the use of removal authority in the conduct of decommissioning activities, consistent with the Policy on Decommissioning of Department of Energy Facilities under the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) (May 22, 1995), and the accompanying Decommissioning Implementation Guide . The Policy and Guide establish the approach agreed upon by the Department of Energy (DOE) and the U.S. Environmental Protection Agency (EPA). It is consistent with CERCLA statutory requirements, as well as CERCLA regulatory requirements found in the National Contingency Plan (NCP), and applicable

108

Reactor Design and Decommissioning - An Overview of International Activities in Post Fukushima Era1 - 12396  

SciTech Connect

Accidents at the Fukushima Dai-ichi reactors as a result of the devastating earthquake and tsunami of March 11, 2011 have not only dampened the nuclear renaissance but have also initiated a re-examination of the design and safety features for the existing and planned nuclear reactors. Even though failures of some of the key site features at Fukushima can be attributed to events that in the past would have been considered as beyond the design basis, the industry as well as the regulatory authorities are analyzing what features, especially passive features, should be designed into the new reactor designs to minimize the potential for catastrophic failures. It is also recognized that since the design of the Fukushima BWR reactors which were commissioned in 1971, many advanced safety features are now a part of the newer reactor designs. As the recovery efforts at the Fukushima site are still underway, decisions with respect to the dismantlement and decommissioning of the damaged reactors and structures have not yet been finalized. As it was with Three Mile Island, it could take several decades for dismantlement, decommissioning and clean up, and the project poses especially tough challenges. Near-term assessments have been issued by several organizations, including the IAEA, the USNRC and others. Results of such investigations will lead to additional improvements in system and site design measures including strengthening of the anti-tsunami defenses, more defense-in-depth features in reactor design, and better response planning and preparation involving reactor sites. The question also arises what would the effect be on the decommissioning scene worldwide, and what would the effect be on the new reactors when they are eventually retired and dismantled. This paper provides an overview of the US and international activities related to recovery and decommissioning including the decommissioning features in the reactor design process and examines these from a new perspective in the post Fukushima -accident era. Accidents at the Fukushima Daiichi reactors in the aftermath of the devastating earthquake and tsunami of March 11, 2011 have slowed down the nuclear renaissance world-wide and may have accelerated decommissioning either because some countries have decided to halt or reduce nuclear, or because the new safety requirements may reduce life-time extensions. Even in countries such as the UK and France that favor nuclear energy production existing nuclear sites are more likely to be chosen as sites for future NPPs. Even as the site recovery efforts continue at Fukushima and any decommissioning decisions are farther into the future, the accidents have focused attention on the reactor designs in general and specifically on the Fukushima type BWRs. The regulatory authorities in many countries have initiated a re-examination of the design of the systems, structures and components and considerations of the capability of the station to cope with beyond-design basis events. Enhancements to SSCs and site features for the existing reactors and the reactors that will be built will also impact the decommissioning phase activities. The newer reactor designs of today not only have enhanced safety features but also take into consideration the features that will facilitate future decommissioning. Lessons learned from past management and operation of reactors as well as the lessons from decommissioning are incorporated into the new designs. However, in the post-Fukushima era, the emphasis on beyond-design-basis capability may lead to significant changes in SSCs, which eventually will also have impact on the decommissioning phase. Additionally, where some countries decide to phase out the nuclear power, many reactors may enter the decommissioning phase in the coming decade. While the formal updating and expanding of existing guidance documents for accident cleanup and decommissioning would benefit by waiting until the Fukushima project has progressed sufficiently for that experience to be reliably interpreted, the development of structured on-li

Devgun, Jas S. [Nuclear Power Technologies, Sargent and Lundy LLC, Chicago, IL (United States); Laraia, Michele [private consultant, formerly from IAEA, Kolonitzgasse 10/2, 1030, Vienna (Austria); Pescatore, Claudio [OECD, Nuclear Energy Agency, Issy-les-Moulineaux, Paris (France); Dinner, Paul [International Atomic Energy Agency, Wagramerstrasse 5, A-1400 Vienna (Austria)

2012-07-01T23:59:59.000Z

109

Radioactive Waste Management and Nuclear Facility Decommissioning Progress in Iraq - 13216  

SciTech Connect

Management of Iraq's radioactive wastes and decommissioning of Iraq's former nuclear facilities are the responsibility of Iraq's Ministry of Science and Technology (MoST). The majority of Iraq's former nuclear facilities are in the Al-Tuwaitha Nuclear Research Center located a few kilometers from the edge of Baghdad. These facilities include bombed and partially destroyed research reactors, a fuel fabrication facility and radioisotope production facilities. Within these facilities are large numbers of silos, approximately 30 process or waste storage tanks and thousands of drums of uncharacterised radioactive waste. There are also former nuclear facilities/sites that are outside of Al-Tuwaitha and these include the former uranium processing and waste storage facility at Jesira, the dump site near Adaya, the former centrifuge facility at Rashdiya and the former enrichment plant at Tarmiya. In 2005, Iraq lacked the infrastructure needed to decommission its nuclear facilities and manage its radioactive wastes. The lack of infrastructure included: (1) the lack of an organization responsible for decommissioning and radioactive waste management, (2) the lack of a storage facility for radioactive wastes, (3) the lack of professionals with experience in decommissioning and modern waste management practices, (4) the lack of laws and regulations governing decommissioning or radioactive waste management, (5) ongoing security concerns, and (6) limited availability of electricity and internet. Since its creation eight years ago, the MoST has worked with the international community and developed an organizational structure, trained staff, and made great progress in managing radioactive wastes and decommissioning Iraq's former nuclear facilities. This progress has been made, despite the very difficult implementing conditions in Iraq. Within MoST, the Radioactive Waste Treatment and Management Directorate (RWTMD) is responsible for waste management and the Iraqi Decommissioning Directorate (IDD) is responsible for decommissioning activities. The IDD and the RWTMD work together on decommissioning projects. The IDD has developed plans and has completed decommissioning of the GeoPilot Facility in Baghdad and the Active Metallurgical Testing Laboratory (LAMA) in Al-Tuwaitha. Given this experience, the IDD has initiated work on more dangerous facilities. Plans are being developed to characterize, decontaminate and decommission the Tamuz II Research Reactor. The Tammuz Reactor was destroyed by an Israeli air-strike in 1981 and the Tammuz II Reactor was destroyed during the First Gulf War in 1991. In addition to being responsible for managing the decommissioning wastes, the RWTMD is responsible for more than 950 disused sealed radioactive sources, contaminated debris from the first Gulf War and (approximately 900 tons) of naturally-occurring radioactive materials wastes from oil production in Iraq. The RWTMD has trained staff, rehabilitated the Building 39 Radioactive Waste Storage building, rehabilitated portions of the French-built Radioactive Waste Treatment Station, organized and secured thousands of drums of radioactive waste organized and secured the stores of disused sealed radioactive sources. Currently, the IDD and the RWTMD are finalizing plans for the decommissioning of the Tammuz II Research Reactor. (authors)

Al-Musawi, Fouad; Shamsaldin, Emad S.; Jasim, Hadi [Ministry of Science and Technology (MoST), Al-Jadraya, P.O. Box 0765, Baghdad (Iraq)] [Ministry of Science and Technology (MoST), Al-Jadraya, P.O. Box 0765, Baghdad (Iraq); Cochran, John R. [Sandia National Laboratories1, New Mexico, Albuquerque New Mexico 87185 (United States)] [Sandia National Laboratories1, New Mexico, Albuquerque New Mexico 87185 (United States)

2013-07-01T23:59:59.000Z

110

Photomultiplier Tube Home  

NLE Websites -- All DOE Office Websites (Extended Search)

Project Homepage Project Homepage Classroom Projects Homepage - Teacher Homepage - Student Homepage Abstract: Photons are created in scintillator devices in most modern particle detectors. These photons yield information about particle collisions that must be measured and decoded. This Website follows the track of a photon as it enters a photomultiplier tube (pmt), an amplifying device that increases the effect of a single photon to levels that are measurable. This signal amplification is crucial; without it, no information exists for decoding. The site presents information regarding the innards of a pmt and allows students to investigate predictive mathematical models describing the signal increase under different, adjustable parameters. Introduction to Research: Photomultipler tubes are omnipresent in particle physics. Understanding the

111

Improving Efficiency of Tube Drawing Bench  

Energy.gov (U.S. Department of Energy (DOE))

Greenville Tube Company, a manufacturer of high-precision, small-diameter stainless steel tubing, conducted an in-house system performance optimization project to improve the efficiency of its No. 6 tube drawing bench. This four-page case study summarizes their experience.

112

Decommissioning of the TA-42 plutonium contaminated incinerator facility  

SciTech Connect

During 1978, a plutonium (/sup 239/Pu) contaminated incinerator facility at the Los Alamos National Laboratory, Los Alamos, New Mexico, was decommissioned. The project involved dismantling the facility and burying the debris at an on-site radioactive solid waste disposal/storage area. Contaminated soil from the 5000 m/sup 2/ area was also buried. The facility was constructed in 1951 to incinerate /sup 239/Pu contaminated wastes. It was later used as a decontamination facility. The major features included a 185-m/sup 2/ floor area control building, incinerator, cyclone dust collector, spray cooler, venturi scrubber, air filter bank, ash separator, and two 140 000-liter ash storage tanks. Six-hundred cubic meters of debris and 1200 m/sup 3/ of soil contaminated with less than 10 nCi /sup 239/Pu per gram of soil were buried at the Laboratory disposal area. Five cubic meters of /sup 239/Pu contaminated ash residues containing more than 10 nCi /sup 239/Pu per gram of waste were packaged and stored to meet the Department of Energy's 20-year retrievable storage criteria. The operation consumed 80 work days and 5800 manhours at a cost of $150 000. This report presents the details concerning decommissioning procedures, the health physics, the waste management, the environmental surveillance results, and a cost breakdown for the operation.

Harper, J.R.; Garde, R.

1981-11-01T23:59:59.000Z

113

FAQS Qualification Card - Deactivation and Decommissioning | Department of  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Deactivation and Decommissioning Deactivation and Decommissioning FAQS Qualification Card - Deactivation and Decommissioning A key element for the Department's Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA). For each functional area, the FAQS identify the minimum technical competencies and supporting knowledge and skills for a typical qualified individual working in the area. FAQC-DeactivationDecommissioning.docx Description Deactivation and Decommissioning Qualification Card More Documents & Publications

114

DOE Policy on Decommissioning DOE Facilities Under CERCLA | Department of  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

DOE Policy on Decommissioning DOE Facilities Under DOE Policy on Decommissioning DOE Facilities Under CERCLA DOE Policy on Decommissioning DOE Facilities Under CERCLA In May 1995, the Department of Energy (DOE) issued a policy in collaboration with the Environmental Protection Agency (EPA) for decommissioning surplus DOE facilities consistent with the requirements of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA). This policy ensures protection of the environment, worker health and public health, provides opportunities for stakeholder involvement, and achieves risk reduction without unnecessary delay. Consistent with the jointly issued "Guidance on Accelerating CERCLA Environmental Restoration at Federal Facilities" (August 22, 1994), this decommissioning policy encourages streamlined decision-making. This

115

Multiple tube premixing device  

DOE Patents (OSTI)

The present application provides a premixer for a combustor. The premixer may include a fuel plenum with a number of fuel tubes and a burner tube with a number of air tubes. The fuel tubes extend about the air tubes.

Uhm, Jong Ho; Naidu, Balachandar; Ziminksy, Willy Steve; Kraemer, Gilbert Otto; Yilmaz, Ertan; Lacy, Benjamin; Stevenson, Christian; Felling, David

2013-08-13T23:59:59.000Z

116

Multiple tube premixing device  

DOE Patents (OSTI)

The present application provides a premixer for a combustor. The premixer may include a fuel plenum with a number of fuel tubes and a burner tube with a number of air tubes. The fuel tubes extend about the air tubes.

Uhm, Jong Ho; Varatharajan, Balachandar; Ziminsky, Willy Steve; Kraemer, Gilbert Otto; Yilmaz, Ertan; Lacy, Benjamin; Stevenson, Christian; Felling, David

2012-12-11T23:59:59.000Z

117

West Valley Demonstration Project  

Energy.gov (U.S. Department of Energy (DOE))

The West Valley Demonstration Project came into being through the West Valley Demonstration Project Act of 1980. The Act requires that the DOE is responsible for solidifying the high-level waste, disposing of waste created by the solidification, and decommissioning the facilities used in the process.

118

NMSS handbook for decommissioning fuel cycle and materials licensees  

SciTech Connect

The US Nuclear Regulatory Commission amended its regulations to set forth the technical and financial criteria for decommissioning licensed nuclear facilities. These regulations were further amended to establish additional recordkeeping requirements for decommissioning; to establish timeframes and schedules for the decommissioning; and to clarify that financial assurance requirements must be in place during operations and updated when licensed operations cease. Reviews of the Site Decommissioning Management Plan (SDMP) program found that, while the NRC staff was overseeing the decommissioning program at nuclear facilities in a manner that was protective of public health and safety, progress in decommissioning many sites was slow. As a result NRC determined that formal written procedures should be developed to facilitate the timely decommissioning of licensed nuclear facilities. This handbook was developed to aid NRC staff in achieving this goal. It is intended to be used as a reference document to, and in conjunction with, NRC Inspection Manual Chapter (IMC) 2605, ``Decommissioning Inspection Program for Fuel Cycle and Materials Licensees.`` The policies and procedures discussed in this handbook should be used by NRC staff overseeing the decommissioning program at licensed fuel cycle and materials sites; formerly licensed sites for which the licenses were terminated; sites involving source, special nuclear, or byproduct material subject to NRC regulation for which a license was never issued; and sites in the NRC`s SDMP program. NRC staff overseeing the decommissioning program at nuclear reactor facilities subject to regulation under 10 CFR Part 50 are not required to use the procedures discussed in this handbook.

Orlando, D.A.; Hogg, R.C.; Ramsey, K.M. [and others

1997-03-01T23:59:59.000Z

119

In Situ Decommissioning (ISD) Concepts and Approaches for Excess Nuclear Facilities Decommissioning End State - 13367  

SciTech Connect

The United States Department of Energy (DOE) currently has numerous radiologically contaminated excess nuclear facilities waiting decommissioning throughout the Complex. The traditional decommissioning end state is complete removal. This commonly involves demolishing the facility, often segregating various components and building materials and disposing of the highly contaminated, massive structures containing tons of highly contaminated equipment and piping in a (controlled and approved) landfill, at times hundreds of miles from the facility location. Traditional demolition is costly, and results in significant risks to workers, as well as risks and costs associated with transporting the materials to a disposal site. In situ decommissioning (ISD or entombment) is a viable alternative to demolition, offering comparable and potentially more protective protection of human health and the environment, but at a significantly reduced cost and worker risk. The Savannah River Site (SRS) has completed the initial ISD deployment for radiologically contaminated facilities. Two reactor (P and R Reactors) facilities were decommissioned in 2011 using the ISD approach through the American Recovery and Reinvestment Act. The SRS ISD approach resolved programmatic, regulatory and technical/engineering issues associated with avoiding the potential hazards and cost associated with generating and disposing of an estimated 124,300 metric tons (153,000 m{sup 3}) of contaminated debris per reactor. The DOE Environmental Management Office of Deactivation and Decommissioning and Facility Engineering, through the Savannah River National Laboratory, is currently investigating potential monitoring techniques and strategies to assess ISD effectiveness. As part of SRS's strategic planning, the site is seeking to leverage in situ decommissioning concepts, approaches and facilities to conduct research, design end states, and assist in regulatory interactions in broad national and international government and private industry decommissioning applications. SRS offers critical services based upon the SRS experience in decommissioning and reactor entombment technology (e.g., grout formulations for varying conditions, structural and material sciences). The SRS ISD approach follows a systems engineering framework to achieve a regulatory acceptable end state based on established protocols, attains the final end state with minimal long stewardship requirements, protects industrial workers, and protects groundwater and the environment. The ISD systems engineering framework addresses key areas of the remedial process planning, technology development and deployment, and assessment to attain the ultimate goal of natural resource stewardship and protecting the public. The development and deployment of the SRS ISD approach has established a path for ISD of other large nuclear facilities in the United States and around the globe as an acceptable remedial alternative for decommissioning nuclear facilities. (authors)

Serrato, Michael G. [Savannah River National Laboratory, Savannah River Nuclear Solutions, Aiken, SC 29808 (United States)] [Savannah River National Laboratory, Savannah River Nuclear Solutions, Aiken, SC 29808 (United States); Musall, John C.; Bergren, Christopher L. [Savannah River Nuclear Solutions, Aiken, SC 29808 (United States)] [Savannah River Nuclear Solutions, Aiken, SC 29808 (United States)

2013-07-01T23:59:59.000Z

120

Technology, safety and costs of decommissioning a reference pressurized water reactor power station: Technical support for decommissioning matters related to preparation of the final decommissioning rule  

SciTech Connect

Preparation of the final Decommissioning Rule by the Nuclear Regulatory Commission (NRC) staff has been assisted by Pacific Northwest Laboratory (PNL) staff familiar with decommissioning matters. These efforts have included updating previous cost estimates developed during the series of studies on conceptually decommissioning reference licensed nuclear facilities for inclusion in the Final Generic Environmental Impact Statement (FGEIS) on decommissioning; documenting the cost updates; evaluating the cost and dose impacts of post-TMI-2 backfits on decommissioning; developing a revised scaling formula for estimating decommissioning costs for reactor plants different in size from the reference pressurized water reactor (PWR) described in the earlier study; defining a formula for adjusting current cost estimates to reflect future escalation in labor, materials, and waste disposal costs; and completing a study of recent PWR steam generator replacements to determine realistic estimates for time, costs and doses associated with steam generator removal during decommissioning. This report presents the results of recent PNL studies to provide supporting information in four areas concerning decommissioning of the reference PWR: updating the previous cost estimates to January 1986 dollars; assessing the cost and dose impacts of post-TMI-2 backfits; assessing the cost and dose impacts of recent steam generator replacements; and developing a scaling formula for plants different in size than the reference plant and an escalation formula for adjusting current cost estimates for future escalation.

Konzek, G.J.; Smith, R.I.

1988-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "tube project decommissioning" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


121

Brookhaven Lab Completes Decommissioning of Graphite Research Reactor:  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Brookhaven Lab Completes Decommissioning of Graphite Research Brookhaven Lab Completes Decommissioning of Graphite Research Reactor: Reactor core and associated structures successfully removed; waste shipped offsite for disposal Brookhaven Lab Completes Decommissioning of Graphite Research Reactor: Reactor core and associated structures successfully removed; waste shipped offsite for disposal September 1, 2012 - 12:00pm Addthis The Brookhaven Graphite Research Reactor’s bioshield, which contains the 700-ton reactor core, is shown prior to decommissioning. The Brookhaven Graphite Research Reactor's bioshield, which contains the 700-ton reactor core, is shown prior to decommissioning. Pictured here is the Brookhaven Graphite Research Reactor, where major decommissioning milestones were recently reached after the remaining radioactive materials from the facility’s bioshield were shipped to a licensed offsite disposal facility.

122

In-Situ Decommissioning: A Strategy for Environmental Management |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

In-Situ Decommissioning: A Strategy for Environmental Management In-Situ Decommissioning: A Strategy for Environmental Management In-Situ Decommissioning: A Strategy for Environmental Management In-Situ Decommissioning (ISD) is an effective decommissioning practice offering a safe and environmentally-favorable alternative to completely demolishing a facility and transporting its debris elsewhere for disposal. Regulatory approval to decommission a facility through ISD is authorized primarily by the Environmental Protection Agency under the Comprehensive Environmental Response, Compensation and Liability Act (CERCLA). In addition, Federal Facility Agreements and local stakeholder agreements have a direct influence on ISD approval and oversight. The ISD approach limits radiation exposure and industrial hazards to workers to a greater extent than larger scale cleanout and demolition.

123

GRR/Section 20 - Plant Decommissioning Overview | Open Energy Information  

Open Energy Info (EERE)

20 - Plant Decommissioning Overview 20 - Plant Decommissioning Overview < GRR Jump to: navigation, search GRR-logo.png GEOTHERMAL REGULATORY ROADMAP Roadmap Home Roadmap Help List of Sections Section 20 - Plant Decommissioning Overview 20PlantDecommissioningOverview (1).pdf Click to View Fullscreen Contact Agencies BLM Regulations & Policies 43 CFR 3263.10-3263.15: Well Abandonment Geothermal Resources Operational Order No.3 Triggers None specified Click "Edit With Form" above to add content 20PlantDecommissioningOverview (1).pdf Error creating thumbnail: Page number not in range. Error creating thumbnail: Page number not in range. Error creating thumbnail: Page number not in range. Flowchart Narrative State and federal laws have specific requirements for the decommissioning process. 20.1 to 20.2 - Will a Geothermal Well be Abandoned?

124

3-D Model for Deactivation & Decommissioning | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

3-D Model for Deactivation & Decommissioning 3-D Model for Deactivation & Decommissioning 3-D Model for Deactivation & Decommissioning The design and production of 3-D scale models that replicate the highly contaminated structures within the nuclear facility would provide a significant improvement in visualization of the work space, which would give managers and supervisors a more powerful tool for planning and communicating safety issues and work sequences to personnel executing the physical D&D tasks. 3-D Model for Deactivation & Decommissioning More Documents & Publications D&D Toolbox Robotic Deployment of High Resolution Laser Imaging for Characterization D&D and Risk Assessment Tools 3-D Model for Deactivation & Decommissioning Deactivation & Decommissioning Knowledge Management Information Tool (D&D

125

Chapter 20 - Uranium Enrichment Decontamination & Decommissioning Fund  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

0. Uranium Enrichment Decontamination and Decommissioning Fund 20-1 0. Uranium Enrichment Decontamination and Decommissioning Fund 20-1 CHAPTER 20 URANIUM ENRICHMENT DECONTAMINATION AND DECOMMISSIONING FUND 1. INTRODUCTION. a. Purpose. To establish policies and procedures for the financial management, accounting, budget preparation, cash management of the Uranium Enrichment Decontamination and Decommissioning Fund, referred to hereafter as the Fund. b. Applicability. This chapter applies to all Departmental elements, including the National Nuclear Security Administration, and activities that are directly or indirectly involved with the Fund. c. Requirements and Sources of the Fund. (1) The Energy Policy Act of 1992 (EPACT) requires DOE to establish and administer the Fund. EPACT authorizes that the

126

Shippingport Station Decommissioning Project decommissioning plan. Volume No. VIII, Part I  

SciTech Connect

Information is presented concerning the radiation work training program; final plant configuration document; engineering requirements for the preparation of detailed procedures; opportunities for cost-schedule reductions; potential risks and problems; cost-benefit criteria and procedure for keeping occupational radiation exposure as low as reasonably achievable; and engineering holds and assumptions.

Not Available

1983-01-01T23:59:59.000Z

127

TransWest Express Transmission Project  

NLE Websites -- All DOE Office Websites (Extended Search)

operate, maintain and decommission the TransWest Express 600-kV Direct Current Transmission Project. TransWest Express, LLC is a whollyowned subsidiary of the Anschutz...

128

Overview of Remote Handling Equipment Used for the NPP A1 Decommissioning - 12141  

SciTech Connect

The first Czechoslovak NPP A1 was in operation from 1972 to 1977 and it was finally shutdown due to an accident (level 4 according to the INES). The presence of radioactive, toxic or hazardous materials limits personnel access to facilities and therefore it is necessary to use remote handling technologies for some most difficult characterization, retrieval, decontamination and dismantling tasks. The history of remote handling technologies utilization started in nineties when the spent nuclear fuel, including those fuel assemblies damaged during the accident, was prepared for the transport to Russia. Subsequent significant development of remote handling equipment continued during implementation of the NPP A1 decommissioning project - Stage I and ongoing Stage II. Company VUJE, Inc. is the general contractor for both mentioned stages of the decommissioning project. Various remote handling manipulators and robotics arms were developed and used. It includes remotely controlled vehicle manipulator MT-15 used for characterisation tasks in hostile and radioactive environment, special robust manipulator DENAR-41 used for the decontamination of underground storage tanks and multi-purposes robotics arms MT-80 and MT-80A developed for variety of decontamination and dismantling tasks. The heavy water evaporator facility dismantling is the current task performed remotely by robotics arm MT-80. The heavy water evaporator is located inside the main production building in the room No. 220 where loose surface contamination varies from 10 Bq/cm{sup 2} to 1x10{sup 3} Bq/cm{sup 2}, dose rate is up to 1.5 mGy/h and the feeding pipeline contained liquid RAW with high tritium content. Presented manipulators have been designed for broad range of decommissioning tasks. They are used for recognition, sampling, waste retrieval from large underground tanks, decontamination and dismantling of technological equipments. Each of the mentioned fields claims specific requirements on design of manipulator, their operation and control systems as well as tools of manipulators. Precise planning of decontamination and dismantling tasks is necessary for its successful performance by remotely controlled manipulator. The example of the heavy water evaporator demonstrates typical procedure for decommissioning of contaminated technological equipment by remotely controlled manipulators - planning of decommissioning tasks, preparatory tasks, modification of applied tools and design of specific supporting constructions for manipulator and finally decontamination and dismantling themselves. Due to the particularly demanding conditions in highly contaminated A1 NPP, a team of experts with special know-how in the field of decommissioning has grown up, and unique technological equipment enabling effective and safe work in environment with a high radiation level has been developed. (authors)

Kravarik, K.; Medved, J.; Pekar, A.; Stubna, M. [VUJE, Inc., Okruzna 5, 918 64 Trnava (Slovakia); Michal, V. [IAEA, Wagramer Strasse 5, P.O.Box 100, A-1400 Vienna (Austria); Vargovcik, L. [ZTS VVU Kosice, Inc., Juzna Trieda 95, 041 24 Kosice (Slovakia)

2012-07-01T23:59:59.000Z

129

Tube furnace  

DOE Patents (OSTI)

A vermiculite insulated tube furnace is heated by a helically-wound resistance wire positioned within a helical groove on the surface of a ceramic cylinder, that in turn is surroundingly disposed about a doubly slotted stainless steel cylindrical liner. For uniform heating, the pitch of the helix is of shorter length over the two end portions of the ceramic cylinder. The furnace is of large volume, provides uniform temperature, offers an extremely precise programmed heating capability, features very rapid cool-down, and has a modest electrical power requirement.

Foster, Kenneth G. (Livermore, CA); Frohwein, Eugene J. (San Ramon, CA); Taylor, Robert W. (Livermore, CA); Bowen, David W. (Livermore, CA)

1991-01-01T23:59:59.000Z

130

E-Print Network 3.0 - application decommissioning models Sample...  

NLE Websites -- All DOE Office Websites (Extended Search)

ECONOMIC MODELING OF RE-LICENSING AND DECOMMISSIONING OPTIONS FOR THE KLAMATH BASIN HYDROELECTRIC... Consultant Report Economic Modeling of Relicensing and Decommissioning Options...

131

Technology, safety and costs of decommissioning a reference boiling water reactor power station: Technical support for decommissioning matters related to preparation of the final decommissioning rule  

SciTech Connect

Preparation of the final Decommissioning Rule by the Nuclear Regulatory Commission (NRC) staff has been assisted by Pacific Northwest Laboratory (PNL) staff familiar with decommissioning matters. These efforts have included updating previous cost estimates developed during the series of studies of conceptually decommissioning reference licensed nuclear facilities for inclusion in the Final Generic Environmental Impact Statement (FGEIS) on decommissioning; documenting the cost updates; evaluating the cost and dose impacts of post-TMI-2 backfits on decommissioning; developing a revised scaling formula for estimating decommissioning costs for reactor plants different in size from the reference boiling water reactor (BWR) described in the earlier study; and defining a formula for adjusting current cost estimates to reflect future escalation in labor, materials, and waste disposal costs. This report presents the results of recent PNL studies to provide supporting information in three areas concerning decommissioning of the reference BWR: updating the previous cost estimates to January 1986 dollars; assessing the cost and dose impacts of post-TMI-2 backfits; and developing a scaling formula for plants different in size than the reference plant and an escalation formula for adjusting current cost estimates for future escalation.

Konzek, G.J.; Smith, R.I.

1988-07-01T23:59:59.000Z

132

Tapered pulse tube for pulse tube refrigerators  

DOE Patents (OSTI)

Thermal insulation of the pulse tube in a pulse-tube refrigerator is maintained by optimally varying the radius of the pulse tube to suppress convective heat loss from mass flux streaming in the pulse tube. A simple cone with an optimum taper angle will often provide sufficient improvement. Alternatively, the pulse tube radius r as a function of axial position x can be shaped with r(x) such that streaming is optimally suppressed at each x.

Swift, Gregory W. (Sante Fe, NM); Olson, Jeffrey R. (San Mateo, CA)

1999-01-01T23:59:59.000Z

133

MCW Laboratory Decommissioning Checklist P.I.:_______________ Date: ___________ LAB DECOMMISSIONING CHECKLIST rev. 12/12/13  

E-Print Network (OSTI)

DECOMMISSIONING CHECKLIST rev. 12/12/13 Timeline Tasks Contacts Completed NA 1 month Inventory sends inventory list to appropriate contact Send email to safetyinfo@mcw.edu "Attn: Chemical, and outline appropriate path of decontamination (e.g. needs oil removed prior to disposal, requires surface

134

Cost Savings through Innovation in Decontamination, Decommissioning, and Dismantlement  

SciTech Connect

The United States Department of Energy (DOE) continually seeks safer and more cost effective technologies for the decontamination and decommissioning (D&D) of nuclear facilities. The Deactivation and Decommissioning Focus Area (DDFA) of the DOE's Office of Science and Technology (OST) sponsored large-scale demonstration and deployment projects (LSDDPs) to help bring new technologies into the D&D programs. The Idaho National Engineering and Environmental Laboratory (INEEL) LSDDP generated a list of needs defining specific problems where improved technologies could be incorporated into ongoing D&D tasks. The needs fell into 5 major categories--characterization, dismantlement, safety, material dispositioning, and decontamination. Technologies were carefully selected that provide a large benefit for a small investment. The technologies must provide significant improvements in cost, safety, radiation exposure, waste volume reduction, or schedule savings and widely applicable throughout the DOE complex. The LSDDP project provided training for the new technologies and worked with technology suppliers to resolve any questions that arose. Since 1998, 26 technologies have been demonstrated or deployed through the LSDDP for the D&D program at the INEEL. Of the 26 demonstrated and deployed technologies, 14 were in characterization, 3 were in decontamination, 4 were in dismantlement, 3 were in safety, and 2 were in material dispositioning. To promote the use of these technologies at other sites within the DOE complex, the LSDDP team published fact sheets, videos, technology summary reports, articles in INEEL star newspaper, posters, and maintained an internet home page on the project. As a result, additional deployments have taken place at the Hanford, Mound, Fernald, Oak Ridge, Ashtabula, and West Valley. Eight of the 26 technologies evaluated were developed in foreign countries. The technologies demonstrated have been shown to be faster, less expensive, and/or safer. The technologies evaluated through the LSDDP have provided improvements in the following D&D areas: robotic underwater characterization of fuel storage pools, characterization of scrap metal for recycle, PCB and RCRA metals analysis in soil, water, paint, or sludge, subsurface characterization, personnel safety, waste disposal, scaffolding use, and remote radiation characterization of buildings and soil. It is estimated that the technologies demonstrated and deployed through this program will save more than $50 million dollars over the next 10 years at the INEEL alone. Of the $50 million estimated dollars saved, about 75% of the savings will come from characterization technologies, 11% from technologies associated with material dispositioning, 10% are associated with dismantlement technologies and the balance split between safety and decontamination.

Neal A. Yancey

2003-02-27T23:59:59.000Z

135

Technology Requirements for In-Situ Decommissioning Workshop Report  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

09-00269, Rev. 0 09-00269, Rev. 0 KEY WORDS: DOE-HQ In situ Decommissioning Entombment Workshop TECHNOLOGY REQUIREMENTS FOR IN SITU DECOMMISSIONING (ISD) WORKSHOP REPORT Patricia L. Lee, John B. Gladden, G. Timothy Jannik, Christine A. Langton, Michael G. Serrato, SRNL Chuck Urland, Erick Reynolds, PEC June 2009 Savannah River National Laboratory Savannah River Nuclear Solutions Savannah River Site

136

License Stewardship Approach to Commercial Nuclear Power Plant Decommissioning  

SciTech Connect

The paper explores both the conceptual approach to decommissioning commercial nuclear facilities using a license stewardship approach as well as the first commercial application of this approach. The license stewardship approach involves a decommissioning company taking control of a site and the 10 CFR 50 License in order to complete the work utilizing the established trust fund. In conclusion: The license stewardship approach is a novel way to approach the decommissioning of a retired nuclear power plant that offers several key advantages to all parties. For the owner and regulators, it provides assurance that the station will be decommissioned in a safe, timely manner. Ratepayers are assured that the work will be completed for the price they already have paid, with the decommissioning contractor assuming the financial risk of decommissioning. The contractor gains control of the assets and liabilities, the license, and the decommissioning fund. This enables the decommissioning contractor to control their work and eliminates redundant layers of management, while bringing more focus on achieving the desired end state - a restored site. (authors)

Daly, P.T.; Hlopak, W.J. [Commercial Services Group, EnergySolutions 1009 Commerce Park, Oak Ridge, TN (United States)

2008-07-01T23:59:59.000Z

137

Ris-R-1250(EN) Decommissioning of the Nuclear  

E-Print Network (OSTI)

Risø-R-1250(EN) Decommissioning of the Nuclear Facilities at Risø National Laboratory Descriptions on request from the Minister of Research and Information Technology. It describes the nuclear facilities;Decommissioning of Risø's nuclear facilities. Descriptions and cost assessment. Risø-R-1250(EN) 3 Contents 1

138

Decontamination, decommissioning, and vendor advertorial issue, 2007  

SciTech Connect

The focus of the July-August issue is on Decontamination, decommissioning, and vendor advertorials. Major articles/reports in this issue include: An interesting year ahead of us, by Tom Christopher, AREVA NP Inc.; U.S.-India Civil Nuclear Cooperation; Decontamination and recycling of retired components, by Sean P. Brushart, Electric Power Research Institute; and, ANO is 33 and going strong, by Tyler Lamberts, Entergy Nuclear Operations, Inc. The industry innovation article is: Continuous improvement process, by ReNae Kowalewski, Arkansas Nuclear One.

Agnihotri, Newal (ed.)

2007-07-15T23:59:59.000Z

139

Tube-in-tube thermophotovoltaic generator  

DOE Patents (OSTI)

A thermophotovoltaic device includes at least one thermal radiator tube, a cooling tube concentrically disposed within each thermal radiator tube and an array of thermophotovoltaic cells disposed on the exterior surface of the cooling tube. A shell having a first end and a second end surrounds the thermal radiator tube. Inner and outer tubesheets, each having an aperture corresponding to each cooling tube, are located at each end of the shell. The thermal radiator tube extends within the shell between the inner tubesheets. The cooling tube extends within the shell through the corresponding apertures of the two inner tubesheets to the corresponding apertures of the two outer tubesheets. A plurality of the thermal radiator tubes can be arranged in a staggered or an in-line configuration within the shell.

Ashcroft, John (Scotia, NY); Campbell, Brian (Scotia, NY); DePoy, David (Clifton Park, NY)

1998-01-01T23:59:59.000Z

140

Technology Requirements for In-Situ Decommissioning Workshop Report |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Services » Site & Facility Restoration » Deactivation & Services » Site & Facility Restoration » Deactivation & Decommissioning (D&D) » D&D Workshops » Technology Requirements for In-Situ Decommissioning Workshop Report Technology Requirements for In-Situ Decommissioning Workshop Report In recognition of the increasing attention being focused on In Situ Decommissioning (ISD or entombment) as an acceptable and beneficial decommissioning end state, EM is developing guidance for the implementation of ISD of excess facilities within the DOE complex. Consistent with the overarching DOE goals for increased personnel and environmental safety, reduced technical uncertainties and risks, and overall gains in efficiencies and effectiveness, EM initiated an ISD Technology Needs Workshop to identify the technical barriers and technology development

Note: This page contains sample records for the topic "tube project decommissioning" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


141

Capturing Process Knowledge for Facility Deactivation and Decommissioning |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Capturing Process Knowledge for Facility Deactivation and Capturing Process Knowledge for Facility Deactivation and Decommissioning Capturing Process Knowledge for Facility Deactivation and Decommissioning The Office of Environmental Management (EM) is responsible for the disposition of a vast number of facilities at numerous sites around the country which have been declared excess to current mission needs. Capturing Process Knowledge for Facility Deactivation and Decommissioning More Documents & Publications Capturing Process Knowledge for Facility Deactivation and Decommissioning Deactivation & Decommissioning Knowledge Management Information Tool (D&D KM-IT) Above on the left is K-25, at Oak Ridge before and after the 844,000 sq-ft demolition. In addition, on the right: K Cooling Tower at Savannah River Site demolition.

142

Technology Requirements for In-Situ Decommissioning Workshop Report |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Services » Site & Facility Restoration » Deactivation & Services » Site & Facility Restoration » Deactivation & Decommissioning (D&D) » D&D Workshops » Technology Requirements for In-Situ Decommissioning Workshop Report Technology Requirements for In-Situ Decommissioning Workshop Report In recognition of the increasing attention being focused on In Situ Decommissioning (ISD or entombment) as an acceptable and beneficial decommissioning end state, EM is developing guidance for the implementation of ISD of excess facilities within the DOE complex. Consistent with the overarching DOE goals for increased personnel and environmental safety, reduced technical uncertainties and risks, and overall gains in efficiencies and effectiveness, EM initiated an ISD Technology Needs Workshop to identify the technical barriers and technology development

143

FROM CONCEPT TO REALITY, IN-SITU DECOMMISSIONING OF THE P AND R REACTORS AT THE SAVANNAH RIVER SITE  

SciTech Connect

SRS recently completed an approximately three year effort to decommission two SRS reactors: P-Reactor (Building 105-P) and R-Reactor (Building 105-R). Completed in December 2011, the concurrent decommissionings marked the completion of two relatively complex and difficult facility disposition projects at the SRS. Buildings 105-P and 105-R began operating as production reactors in the early 1950s with the mission of producing weapons material (e.g., tritium and plutonium-239). The 'P' Reactor and was shutdown in 1991 while the 'R' Reactor and was shutdown in 1964. In the intervening period between shutdown and deactivation & decommissioning (D&D), Buildings 105-P and 105-R saw limited use (e.g., storage of excess heavy water and depleted uranium oxide). For Building 105-P, deactivation was initiated in April 2007 and was essentially complete by June 2010. For Building 105-R, deactivation was initiated in August 2008 and was essentially complete by September 2010. For both buildings, the primary objective of deactivation was to remove/mitigate hazards associated with the remaining hazardous materials, and thus prepare the buildings for in-situ decommissioning. Deactivation removed the following hazardous materials to the extent practical: combustibles/flammables, residual heavy water, acids, friable asbestos (as needed to protect workers performing deactivation and decommissioning), miscellaneous chemicals, lead/brass components, Freon(reg sign), oils, mercury/PCB containing components, mold and some radiologically-contaminated equipment. In addition to the removal of hazardous materials, deactivation included the removal of hazardous energy, exterior metallic components (representing an immediate fall hazard), and historical artifacts along with the evaporation of water from the two Disassembly Basins. Finally, so as to facilitate occupancy during the subsequent in-situ decommissioning, deactivation implemented repairs to the buildings and provided temporary power.

Musall, J.; Blankenship, J.; Griffin, W.

2012-01-09T23:59:59.000Z

144

Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 12  

SciTech Connect

The 664 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the twelfth in a series of reports prepared annually for the US Department of Energy Remedial Action Programs. Citations to foreign and domestic literature of all types -- technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions -- have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy Remedial Action Programs. Major sections are (1) Decontamination and Decommissioning Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Program, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Uranium Mill Tailings Management, (7) Technical Measurements Center, and (8) Environmental Restoration Program. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and key word. This report is a product of the Remedial Action Program Information Center (RAPIC), which selects, analyzes, and disseminates information on environmental restoration and remedial actions. RAPIC staff and resources are available to meet a variety of information needs. Contact the center at FTS 624-7764 or (615) 574-7764.

Not Available

1991-09-01T23:59:59.000Z

145

Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 12. Environmental Restoration Program  

SciTech Connect

The 664 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the twelfth in a series of reports prepared annually for the US Department of Energy Remedial Action Programs. Citations to foreign and domestic literature of all types -- technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions -- have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy Remedial Action Programs. Major sections are (1) Decontamination and Decommissioning Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Program, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Uranium Mill Tailings Management, (7) Technical Measurements Center, and (8) Environmental Restoration Program. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and key word. This report is a product of the Remedial Action Program Information Center (RAPIC), which selects, analyzes, and disseminates information on environmental restoration and remedial actions. RAPIC staff and resources are available to meet a variety of information needs. Contact the center at FTS 624-7764 or (615) 574-7764.

Not Available

1991-09-01T23:59:59.000Z

146

High-Pressure Tube Trailers and Tanks  

Energy.gov (U.S. Department of Energy (DOE))

Presentation on High-Pressure Tube Trailers and Tanks for the DOE Hydrogen Delivery High-Pressure Tanks and Analysis Project Review Meeting held February 8-9, 2005 at Argonne National Laboratory

147

Decommissioning and Demolition of a Redundant UK Research Facility at AWE Aldermaston - 12453  

SciTech Connect

The redundant two-storey brick built research facility on the AWE Site at Aldermaston, UK is in the closing stages of decommissioning and demolition. The facility was used for a variety of purposes up to 1995 predominately involving the use of alpha-emitting isotopes. The two main areas of alpha-based contamination have been decommissioned with the removal of hot -boxes and fume cupboards on the ground floor and HEPA filter units and ventilation equipment on the first floor. Many of these activities were undertaken using both airline fed suits, (supplied via a free standing mobile unit), and full face respirators. Asbestos materials were located and cleared from the first floor by specialist contractor. All sections of active drain running from the building to the site active effluent disposal system were removed early in the program using established techniques with specialist monitoring equipment used to provide confidence in the data required for disposal of the decommissioning debris. In particular a dedicated High Resolution Gamma Spectrometer (radioactive materials scanning unit) was utilized to categorise waste drums and wrapped packages. The building has been decommissioned and the monitoring and sampling of the structure was completed in November 2011 - the results demonstrating that the building was clear of contamination in accordance with UK clearance and exemption requirements. The demolition plan was developed and implemented in December with site excavation of foundations and site clearance currently ongoing in preparation for final site backfill activities and project close. A number of useful lessons have been learnt during the operations and are set out at the rear of the main text. (authors)

Pritchard, Paul [Atomic Weapons Establishment, Aldermaston (United Kingdom)

2012-07-01T23:59:59.000Z

148

Idaho Site Closes Out Decontamination and Decommissioning Project...  

Energy Savers (EERE)

about 440 Million under Cost November 8, 2012 - 12:00pm Addthis Workers demolish the Test Area North Hot Shop Complex, shown here. Workers demolish the Test Area North Hot Shop...

149

DECOMMISSIONING OF A CAESIUM-137 SEALED SOURCE PRODUCTION FACILITY  

SciTech Connect

Amersham owns a former Caesium-137 sealed source production facility. They commissioned RWE NUKEM to carry out an Option Study to determine a strategy for the management of this facility and then the subsequent decommissioning of it. The decommissioning was carried out in two sequential phases. Firstly robotic decommissioning followed by a phase of manual decommissioning. This paper describes the remote equipment designed built and operated, the robotic and manual decommissioning operations performed, the Safety Management arrangements and summarizes the lessons learned. Using the equipment described the facility was dismantled and decontaminated robotically. Some 2300kg of Intermediate Level Waste containing in the order of 4000Ci were removed robotically from the facility. Ambient dose rates were reduced from 100's of R per hour {gamma} to 100's of mR per hour {gamma}. The Telerobotic System was then removed to allow man access to complete the decommissioning. Manual decommissioning reduced ambient dose rates further to less than 1mR per hour {gamma} and loose contamination levels to less than 0.25Bq/cm2. This allowed access to the facility without respiratory protection.

Murray, A.; Abbott, H.

2003-02-27T23:59:59.000Z

150

Some aspects of the decommissioning of nuclear power plants  

SciTech Connect

The major factors influencing the choice of a national concept for the decommissioning of nuclear power plants are examined. The operating lifetimes of power generating units with nuclear reactors of various types (VVER-1000, VVER-440, RBMK-1000, EGP-6, and BN-600) are analyzed. The basic approaches to decommissioning Russian nuclear power plants and the treatment of radioactive waste and spent nuclear fuel are discussed. Major aspects of the ecological and radiation safety of personnel, surrounding populations, and the environment during decommissioning of nuclear installations are identified.

Khvostova, M. S., E-mail: marinakhvostova@list.ru [St. Petersburg State Maritime Technical University (Sevmashvtuz), Severodvinsk Branch (Russian Federation)

2012-03-15T23:59:59.000Z

151

Finding of no significant impact, decontamination and decommissioning of Battelle Columbus Laboratories in Columbus and West Jefferson, Ohio  

SciTech Connect

This Environmental Assessment has been developed by the Department of Energy in accordance with the requirements of the National Environmental Policy Act of 1969 for the proposed decommissioning of contaminated areas at the Battelle Memorial Institute, Columbus, Ohio. The discussions in Section 1.0 provide general background information on the proposed action. Section 2.0 describes the existing radiological and non-radiological condition of the Battelle Columbus Laboratories. Section 3.0 identifies the alternatives considered for the proposed action and describes in detail the proposed decommissioning project. Section 4.0 evaluates the potential risks the project poses to human health and the environment. Section 5.0 presents the Department of Energy's proposed action. As a result of nuclear research and development activities conducted over a period of approximately 43 years performed for the Department of Energy, its predecessor agencies, and under commercial contracts, the 15 buildings became contaminated with varying amounts of radioactive material. The Department of Energy no longer has a need to utilize the facilities and is contractually obligate to remove that contamination such that they can be used by their owners without radiological restrictions. This Environmental Assessment for the Battelle Columbus Laboratories Decommissioning Project is consistent with the direction from the Secretary of Energy that public awareness and participation be considered in sensitive projects and is an appropriate document to determine action necessary to satisfy the requirements of the National Environmental Policy Act. 30 refs., 6 figs., 9 tabs.

Not Available

1990-01-01T23:59:59.000Z

152

FAQS Job Task Analyses - Deactivation and Decommissioning  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Functional Area Qualification Standard Functional Area Qualification Standard Deactivation & Decommissioning (D&D) DOE-STD-1166-2003 Step 1 Identify and evaluate tasks - Develop a comprehensive list of tasks that define the job. o A great starting point is the list of Duties and Responsibilities from the FAQS. o Give careful thought to additional tasks that could be considered. o Don't worry about deleting tasks at this point - that is a part of the process further down. - List the tasks (and their sources, e.g., Duties and Responsibilities #1) in the chart below. - Discuss each task as a group and come to a consensus pertaining to Importance and Frequency of the task (i.e., each team member can consent to the assigned value, even if they don't exactly agree with it).

153

Decontamination, decommissioning, and vendor advertorial issue, 2008  

SciTech Connect

The focus of the July-August issue is on Decontamination, decommissioning, and vendor advertorials. Articles and reports in this issue include: D and D technical paper summaries; The role of nuclear power in turbulent times, by Tom Chrisopher, AREVA, NP, Inc.; Enthusiastic about new technologies, by Jack Fuller, GE Hitachi Nuclear Energy; It's important to be good citizens, by Steve Rus, Black and Veatch Corporation; Creating Jobs in the U.S., by Guy E. Chardon, ALSTOM Power; and, and, An enviroment and a community champion, by Tyler Lamberts, Entergy Nuclear Operations, Inc. The Industry Innovations article is titled Best of the best TIP achievement 2008, by Edward Conaway, STP Nuclear Operating Company.

Agnihotri, Newal (ed.)

2008-07-15T23:59:59.000Z

154

Plan for fully decontaminating and decommissioning of the Westinghouse Advanced Reactors Division Fuel Laboratories at Cheswick, Revision 3  

SciTech Connect

The project scope of work included the complete decontamination and decommissioning (D and D) of the Westinghouse ARD Fuel Laboratories at the Cheswick Site in the shortest possible time. This has been accomplished in the following four phases: (1) preparation of documents and necessary paperwork; packaging and shipping of all special nuclear materials in an acceptable form to a reprocessing agency; (2) decontamination of all facilities, glove boxes and equipment; loading of generated waste into bins, barrels and strong wooden boxes; (3) shipping of all bins, barrels and boxes containing waste to the designated burial site; removal of all utility services from the laboratories; (4) final survey of remaining facilities and certification for nonrestricted use; preparation of final report. This volume contains the following 3 attachments: (1) Plan for Fully Decontamination and Decommissioning of the Westinghouse Advanced Reactors Division Fuel Laboratories at Cheswick; (2) Environmental Assessment for Decontamination and Decommissioning the Westinghouse Advanced Reactors Division Plutonium Fuel Laboratories, Cheswick, PA; and (3) WARD-386, Quality Assurance Program Description for Decontamination and Decommissioning Activities.

Not Available

1982-01-01T23:59:59.000Z

155

Task 21 - Development of Systems Engineering Applications for Decontamination and Decommissioning Activities  

SciTech Connect

The objectives of this task are to: Develop a model (paper) to estimate the cost and waste generation of cleanup within the Environmental Management (EM) complex; Identify technologies applicable to decontamination and decommissioning (D and D) operations within the EM complex; Develop a database of facility information as linked to project baseline summaries (PBSs). The above objectives are carried out through the following four subtasks: Subtask 1--D and D Model Development, Subtask 2--Technology List; Subtask 3--Facility Database, and Subtask 4--Incorporation into a User Model.

Erickson, T.A.

1998-11-01T23:59:59.000Z

156

EA-1053: Decontaminating and Decommissioning the General Atomics Hot Cell  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

3: Decontaminating and Decommissioning the General Atomics 3: Decontaminating and Decommissioning the General Atomics Hot Cell Facility, San Diego, California EA-1053: Decontaminating and Decommissioning the General Atomics Hot Cell Facility, San Diego, California SUMMARY This EA evaluates the environmental impacts of the proposal for low-level radioactive and mixed wastes generated by decontaminating and decommissioning activities at the U.S. Department of Energy's General Atomics' Hot Cell Facility would be transported to either a DOE owned facility, such as the Hanford site in Washington, or to a commercial facility, such as Envirocare in Utah, for treatment and/or storage and disposal. PUBLIC COMMENT OPPORTUNITIES None available at this time. DOCUMENTS AVAILABLE FOR DOWNLOAD August 14, 1995 EA-1053: Finding of No Significant Impact

157

Policy Statement 3, Board Oversight of Department of Energy Decommissioning  

NLE Websites -- All DOE Office Websites (Extended Search)

3 3 Date: August 19, 1996 Subject Policy Statement on Board oversight of Department of Energy decommissioning activities at defense nuclear facilities. Summary This policy statement describes the decommissioning phase of a DOE defense nuclear facility and identifies the Board's safety oversight responsibilities for decommisioning activities. John T. Conway, Chairman Congress directed the Defense Nuclear Facilities Safety Board (Board) to oversee Department of Energy (DOE) practices at defense nuclear facilities that could adversely affect public health and safety during any stage in the life cycle of those facilities, from design, construction, and operation through decommissioning. The Board's objective during decommissioning is identical to its objective during any other phase of a facility's life cycle: to ensure that DOE provides adequate protection of worker and public health and safety at defense nuclear facilities. Congress specifically tasked the Board with reviewing and evaluating:

158

DEACTIVATION AND DECOMMISSIONING (D AND D) TECHNOLOGY INTEGRATION  

SciTech Connect

As part of the ongoing task of making Deactivation and Decommissioning (D&D) operations more efficient, this subtask has addressed the need to integrate existing characterization technologies with decontamination technologies in order to provide real-time data on the progress of contamination removal. Specifically, technologies associated with concrete decontamination and/or removal have been examined with the goal of integrating existing technologies and commercializing the resulting hybrid. The Department of Energy (DOE) has estimated that 23 million cubic meters of concrete will require disposition as 1200 buildings undergo the D&D process. All concrete removal to be performed will also necessitate extensive use of characterization techniques. The in-process characterization presents the most potential for improvement and cost-savings as compared to other types. Current methods for in-process characterization usually require cessation of work to allow for radiation surveys to assess the rate of decontamination. Combining together decontamination and characterization technologies would allow for in-process evaluation of decontamination efforts. Since the present methods do not use in-process evaluations for the progress of decontamination, they may allow for ''overremoval'' of materials (removal of contaminated along with non-contaminated materials). Overremoval increases the volume of waste and therefore the costs associated with disposal. Integrating technologies would facilitate the removal of only contaminated concrete and reduce the total volume of radioactive waste, which would be disposed of. This would eventually ensure better productivity and time savings. This project presents a general procedure to integrate the above-mentioned technologies in the form of the Technology Integration Module (TIM) along with combination lists of commercially available decontamination and characterization technologies. The scope of the project has also been expanded by FIU-HCET to evaluate a technology integration--shot blasting technology and an ultrasonic rangefinder, which are decontamination and sensor technology, respectively.

M.A. Ebadian, Ph.D.

1999-01-01T23:59:59.000Z

159

Nuclear facility decommissioning and site remedial actions: a selected bibliography. Volume 5  

SciTech Connect

This bibliography of 756 references with abstracts on the subject of nuclear facility decommissioning, uranium mill tailings management, and site remedial actions is the fifth in a series of annual reports prepared for the US Department of Energy, Division of Remedial Action Projects. Foreign as well as domestic literature of all types - technical reports, progress reports, journal articles, conference papers, symposium proceedings, theses, books, patents, legislation, and research project descriptions - has been included in this publication. The bibliography contains scientific (basic research as well as applied technology), economic, regulatory, and legal literature pertinent to the US Department of Energy's Remedial Action Program. Major chapters are: (1) Surplus Facilities Management Program; (2) Nuclear Facilities Decommissioning; (3) Formerly Utilized Sites Remedial Action Program; (4) Uranium Mill Tailings Remedial Action Program; (5) Grand Junction Remedial Action Program; (6) Uranium Mill Tailings Management; and (7) Technical Measurements Center. Chapter sections for chapters 1, 2, 4, and 6 include Design, Planning, and Regulations; Environmental Studies and Site Surveys; Decontamination Studies; Dismantlement and Demolition; Site Stabilization and Reclamation; Waste Disposal; Remedial Action Experience; and General Studies. The references within each chapter or section are arranged alphabetically by leading author. References having no individual author are arranged by corporate author or by title. Indexes are provided for the categories of author, corporate affiliation, title, publication description, geographic location, and keywords. The Appendix contains a list of frequently used acronyms.

Owen, P.T.; Knox, N.P.; Chilton, B.D.; Baldauf, M.F.

1984-09-01T23:59:59.000Z

160

Other Projects [Laser Applications Laboratory] - Nuclear Engineering  

NLE Websites -- All DOE Office Websites (Extended Search)

Other Projects Other Projects Capabilities Engineering Experimentation Reactor Safety Experimentation Aerosol Experiments System Components Laser Applications Overview Laser Oil & Gas Well Drilling Laser Heat Treatment Laser Welding of Metals On-line Monitoring Laser Beam Delivery Laser Glazing of Railroad Rails High Power Laser Beam Delivery Decontamination and Decommissioning Refractory Alloy Welding Robots Applications Other Facilities Other Capabilities Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE on Flickr Laser Applications Laboratory Other projects Bookmark and Share HIGH POWER LASER BEAM DELIVERY High-power laser-beam delivery with conventional and fiber optics DECONTAMINATION & DECOMMISSIONING Laser processing technology for decontamination of surfaces

Note: This page contains sample records for the topic "tube project decommissioning" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


161

The Chernobyl NPP decommissioning: Current status and alternatives  

SciTech Connect

After the Chernobyl accident of April 26, 1986, many contradictory decisions were taken concerning the Chernobyl nuclear power plant (NPP) future. The principal source of contradictions was a deadline for a final shutdown of the Chernobyl NPP units. Alterations in a political and socioeconomic environment resulted in the latest decision of the Ukrainian Authorities about 2000 as a deadline for a beginning of the Chernobyl NPP decommissioning. The date seems a sound compromise among the parties concerned. However, in order to meet the data a lot of work should be done. First of all, a decommissioning strategy has to be established. The problem is complicated due to both site-specific aspects and an absence of proven solutions for the RBMK-type reactor decommissioning. In the paper the problem of decommissioning option selection is considered taking into account an influence of the following factors: relevant legislative and regulatory requirements; resources required to carry out decommissioning (man-power, equipment, technologies, waste management infrastructure, etc.); radiological and physical status of the plant, including structural integrity and predictable age and weather effects; impact of planned activities at the destroyed unit 4 and within the 30-km exclusion zone of the Chernobyl NPP; planed use of the site; socio-economic considerations.

Mikolaitchouk, H. [Atomaudit Ltd., Kiev (Ukraine); Steinberg, N. [Atomaudit Ltd., Kiev (Ukraine)

1996-08-01T23:59:59.000Z

162

Mobile worksystems for decontamination and decommissioning operations. Final report  

SciTech Connect

This project is an interdisciplinary effort to develop effective mobile worksystems for decontamination and decommissioning (D&D) of facilities within the DOE Nuclear Weapons Complex. These mobile worksystems will be configured to operate within the environmental and logistical constraints of such facilities and to perform a number of work tasks. Our program is designed to produce a mobile worksystem with capabilities and features that are matched to the particular needs of D&D work by evolving the design through a series of technological developments, performance tests and evaluations. The Phase I effort was based on a robot called the Remote Work Vehicle (RWV) that was previously developed by CMU for use in D&D operations at the Three Mile Island Unit 2 Reactor Building basement. During Phase I of this program, the RWV was rehabilitated and upgraded with contemporary control and user interface technologies and used as a testbed for remote D&D operations. We established a close working relationship with the DOE Robotics Technology Development Program (RTDP). In the second phase, we designed and developed a next generation mobile worksystem, called Rosie, and a semi-automatic task space scene analysis system, called Artisan, using guidance from RTDP. Both systems are designed to work with and complement other RTDP D&D technologies to execute selective equipment removal scenarios in which some part of an apparatus is extricated while minimally disturbing the surrounding objects. RTDP has identified selective equipment removal as a timely D&D mission, one that is particularly relevant during the de-activation and de-inventory stages of facility transitioning as a means to reduce the costs and risks associated with subsequent surveillance and monitoring. In the third phase, we tested and demonstrated core capabilities of Rosie and Artisan; we also implemented modifications and enhancements that improve their relevance to DOE`s facility transitioning mission.

NONE

1997-02-01T23:59:59.000Z

163

Microhole Tubing Bending Report  

DOE Data Explorer (OSTI)

A downhole tubing bending study was made and is reported herein. IT contains a report and 2 excel spreadsheets to calculate tubing bending and to estimate contact points of the tubing to the drilled hole wall (creating a new support point).

Oglesby, Ken

164

Project  

NLE Websites -- All DOE Office Websites (Extended Search)

Exploring the Standard Model Exploring the Standard Model       You've heard a lot about the Standard Model and the pieces are hopefully beginning to fall into place. However, even a thorough understanding of the Standard Model is not the end of the story but the beginning. By exploring the structure and details of the Standard Model we encounter new questions. Why do the most fundamental particles have the particular masses we observe? Why aren't they all symmetric? How is the mass of a particle related to the masses of its constituents? Is there any other way of organizing the Standard Model? The activities in this project will elucidate but not answer our questions. The Standard Model tells us how particles behave but not necessarily why they do so. The conversation is only beginning. . . .

165

Technology needs for decommissioning and decontamination  

SciTech Connect

This report summarizes the current view of the most important decontamination and decommissioning (D & D) technology needs for the US Department of Energy facilities for which the D & D programs are the responsibility of Martin Marietta Energy Systems, Inc. The source of information used in this assessment was a survey of the D & D program managers at each facility. A summary of needs presented in earlier surveys of site needs in approximate priority order was supplied to each site as a starting point to stimulate thinking. This document reflects a brief initial assessment of ongoing needs; these needs will change as plans for D & D are finalized, some of the technical problems are solved through successful development programs, and new ideas for D and D technologies appear. Thus, this assessment should be updated and upgraded periodically, perhaps, annually. This assessment differs from others that have been made in that it directly and solely reflects the perceived need for new technology by key personnel in the D & D programs at the various facilities and does not attempt to consider the likelihood that these technologies can be successfully developed. Thus, this list of technology needs also does not consider the cost, time, and effort required to develop the desired technologies. An R & D program must include studies that have a reasonable chance for success as well as those for which there is a high need. Other studies that considered the cost and probability of successful development as well as the need for new technology are documented. However, the need for new technology may be diluted in such studies; this document focuses only on the need for new technology as currently perceived by those actually charged with accomplishing D & D.

Bundy, R.D.; Kennerly, J.M.

1993-12-01T23:59:59.000Z

166

Confidentiality Agreement between the Nuclear Decommissioning Authority and US Department of Energy  

Energy.gov (U.S. Department of Energy (DOE))

Confidentiality Agreement between the Nuclear Decommissioning Authority in UK and US Department of Energy

167

In-Situ Decommissioning: A Strategy for Environmental Management  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

In-Situ Decommissioning In-Situ Decommissioning A Strategy for Environmental Management Reducing the Footprint of the Cold War For over a decade, the Department of Energy has focused on reducing the footprint of 60 years of nuclear research and weapons testing and production. While these facilities are no longer needed, they exist with varying degrees of radiation contamination from years of operation. Deactivation & Decommissioning (D&D) is the process of closing down a nuclear facility and placing it in a state that reduces or eliminates risk to the pub lic and the environment. This generally includes demolition and transport of the debris to a disposal facility. Another alternative is to dispose of the facility in place (i.e., in-situ). The concept of In-Situ Decommis-

168

Completion of decommissioning: Monitoring for site release and license termination  

SciTech Connect

To request termination of a license upon completion of dismantling or decommissioning activities, documenting any residual radioactivity to show that the levels are environmentally acceptable will be necessary. When the regulators approve the decommissioning plan, they establish what the release criteria for the decommissioned site will be at the time of the site release and license termination. The criteria are numeric guidelines for direct radiation in soils and on surfaces. If the regulatory body finds that the measured on-site values are below the guidelines, the site will be acceptable for unrestricted release (no radiological controls or future use). If areas are found above those values, more decontamination or cleanup of these areas may be required unless the regulatory body grants an exemption.

Boing, L.E.

1997-08-01T23:59:59.000Z

169

A critical review of nuclear power plant decommissioning planning studies  

Science Journals Connector (OSTI)

During the past decade there have been at least ten major efforts to perform comprehensive, analytical studies of the complex issues associated with decommissioning civilian nuclear power plants. These planning efforts are reviewed, using the standard framework of technology assessment. In particular, each study is analysed to determine the degree to which formal methods of decision analysis have been employed to evaluate options and make recommendations and the degree to which formal methods of consensus have been employed to engage citizen involvement and promote public acceptance. Not unexpectedly, we find that the greatest strides in decommissioning analyses have been made in forecasting the economic costs of decommissioning to licensees. Comparatively few improvements have been made in the processes used to compare the impacts of alternative technologies more broadly, or to address the legitimate concerns of interested parties more widely.

W.Timothy Lough; K.Preston White Jr.

1990-01-01T23:59:59.000Z

170

DEACTIVATION AND DECOMMISSIONING PLANNING AND ANALYSIS WITH GEOGRAPHIC INFORMATION SYSTEMS  

SciTech Connect

From the mid-1950's through the 1980's, the U.S. Department of Energy's Savannah River Site produced nuclear materials for the weapons stockpile, for medical and industrial applications, and for space exploration. Although SRS has a continuing defense-related mission, the overall site mission is now oriented toward environmental restoration and management of legacy chemical and nuclear waste. With the change in mission, SRS no longer has a need for much of the infrastructure developed to support the weapons program. This excess infrastructure, which includes over 1000 facilities, will be decommissioned and demolished over the forthcoming years. Dispositioning facilities for decommissioning and deactivation requires significant resources to determine hazards, structure type, and a rough-order-of-magnitude estimate for the decommissioning and demolition cost. Geographic information systems (GIS) technology was used to help manage the process of dispositioning infrastructure and for reporting the future status of impacted facilities.

Bollinger, J; William Austin, W; Larry Koffman, L

2007-09-17T23:59:59.000Z

171

Revised Analyses of Decommissioning Reference Non-Fuel-Cycle Facilities  

SciTech Connect

Cost information is developed for the conceptual decommissioning of non-fuel-cycle nuclear facilities that represent a significant decommissioning task in terms of decontamination and disposal activities. This study is a re-evaluation of the original study (NUREG/CR-1754 and NUREG/CR-1754, Addendum 1). The reference facilities examined in this study are the same as in the original study and include: a laboratory for the manufacture of {sup 3}H-labeled compounds; a laboratory for the manufacture of {sup 14}C-labeled compounds; a laboratory for the manufacture of {sup 123}I-labeled compounds; a laboratory for the manufacture of {sup 137}Cs sealed sources; a laboratory for the manufacture of {sup 241}Am sealed sources; and an institutional user laboratory. In addition to the laboratories, three reference sites that require some decommissioning effort were also examined. These sites are: (1) a site with a contaminated drain line and hold-up tank; (2) a site with a contaminated ground surface; and (3) a tailings pile containing uranium and thorium residues. Decommissioning of these reference facilities and sites can be accomplished using techniques and equipment that are in common industrial use. Essentially the same technology assumed in the original study is used in this study. For the reference laboratory-type facilities, the study approach is to first evaluate the decommissioning of individual components (e.g., fume hoods, glove boxes, and building surfaces) that are common to many laboratory facilities. The information obtained from analyzing the individual components of each facility are then used to determine the cost, manpower requirements and dose information for the decommissioning of the entire facility. DECON, the objective of the 1988 Rulemaking for materials facilities, is the decommissioning alternative evaluated for the reference laboratories because it results in the release of the facility for restricted or unrestricted use as soon as possible. For a facility, DECON requires that contaminated components either be: (1) decontaminated to restricted or unrestricted release levels or (2) packaged and shipped to an authorized disposal site. This study considers unrestricted release only. The new decommissioning criteria of July 1997 are too recent for this study to include a cost analysis of the restricted release option, which is now allowed under these new criteria. The costs of decommissioning facility components are generally estimated to be in the range of $140 to $27,000, depending on the type of component, the type and amount of radioactive contamination, the remediation options chosen, and the quantity of radioactive waste generated from decommissioning operations. Estimated costs for decommissioning the example laboratories range from $130,000 to $205,000, assuming aggressive low-level waste (LLW) volume reduction. If only minimal LLW volume reduction is employed, decommissioning costs range from $150,000 to $270,000 for these laboratories. On the basis of estimated decommissioning costs for facility components, the costs of decommissioning typical non-fuel-cycle laboratory facilities are estimated to range from about $25,000 for the decommissioning of a small room containing one or two fume hoods to more than $1 million for the decommissioning of an industrial plant containing several laboratories in which radiochemicals and sealed radioactive sources are prepared. For the reference sites of this study, the basic decommissioning alternatives are: (1) site stabilization followed by long-term care and (2) removal of the waste or contaminated soil to an authorized disposal site. Cost estimates made for decommissioning three reference sites range from about $130,000 for the removal of a contaminated drain line and hold-up tank to more than $23 million for the removal of a tailings pile that contains radioactive residue from ore-processing operations in which tin slag is processed for the recovery of rare metals. Total occupational radiation doses generally range from 0.00007 person-rem to 13 person-rem for

MC Bierschbach; DR Haffner; KJ Schneider; SM Short

2002-12-01T23:59:59.000Z

172

Final EIS for Decommissioning and/or Long-Term Stewardship at the WVDP and Western New York Nuclear Service Center  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

DOE/EIS-0226 DOE/EIS-0226 January 2010 Final Environmental Impact Statement for Decommissioning and/or Long-Term Stewardship at the West Valley Demonstration Project and Western New York Nuclear Service Center A Summary and Guide for Stakeholders The West Valley Site Availability of the Final EIS for Decommissioning and/or Long-Term Stewardship at the West Valley Demonstration Project and Western New York Nuclear Service Center For further information on this Final EIS, or to request a copy of the EIS or references, please contact: Catherine Bohan, EIS Document Manager West Valley Demonstration Project U.S. Department of Energy Ashford Office Complex 9030 Route 219 West Valley, NY 14171 Telephone: 716-942-4159 Fax: 716-942-4703 E-mail: catherine.m.bohan@wv.doe.gov

173

High Flux Beam Reactor | Environmental Restoration Projects | BNL  

NLE Websites -- All DOE Office Websites (Extended Search)

Environmental Protection Division Environmental Protection Division Home Reactor Projects Celebrating DOE's Cleanup Accomplishments (PDF) Brookhaven Graphite Research Reactor(BGRR) BGRR Overview BGRR Complex Description Decommissioning Decision BGRR Complex Cleanup Actions BGRR Documents BGRR Science & Accomplishments High Flux Beam Reactor (HFBR) HFBR Overview HFBR Complex Description Decommissioning Decision HFBR Complex Cleanup Actions HFBR Documents HFBR Science & Accomplishments Groundwater Protection Group Environmental Protection Division Contact > See also: HFBR Science & Accomplishments High Flux Beam Reactor Under the U.S. Department of Energy (DOE), the High Flux Beam Reactor (HFBR) at Brookhaven National Laboratory (BNL) underwent stabilization and partial decommissioning to prepare the HFBR confinement for long-term safe

174

Nuclear facility decommissioning and site remedial actions. Volume 6. A selected bibliography  

SciTech Connect

This bibliography of 683 references with abstracts on the subject of nuclear facility decommissioning, uranium mill tailings management, and site remedial actions is the sixth in a series of annual reports prepared for the US Department of Energy's Remedial Action Programs. Foreign as well as domestic literature of all types - technical reports, progress reports, journal articles, conference papers, symposium proceedings, theses, books, patents, legislation, and research project descriptions - has been included. The bibliography contains scientific (basic research as well as applied technology), economic, regulatory, and legal literature pertinent to the US Department of Energy's remedial action program. Major chapters are: (1) Surplus Facilities Management Program; (2) Nuclear Facilities Decommissioning; (3) Formerly Utilized Sites Remedial Action Program; (4) Facilities Contaminated with Natural Radioactivity; (5) Uranium Mill Tailings Remedial Action Program; (6) Grand Junction Remedial Action Program; (7) Uranium Mill Tailings Management; (8) Technical Measurements Center; and (9) General Remedial Action Program Studies. Chapter sections for chapters 1, 2, 5, and 7 include Design, Planning, and Regulations; Environmental Studies and Site Surveys; Health, Safety, and Biomedical Studies; Decontamination Studies; Dismantlement and Demolition; Site Stabilization and Reclamation; Waste Disposal; Remedial Action Experience; and General Studies. The references within each chapter or section are arranged alphabetically by leading author. References having no individual author are arranged by corporate affiliation or by publication description.

Owen, P.T.; Michelson, D.C.; Knox, N.P.

1985-09-01T23:59:59.000Z

175

CX-005663: Categorical Exclusion Determination | Department of...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Exclusion Determination CX-005663: Categorical Exclusion Determination Vortex Tube Project Decommissioning Project CX(s) Applied: B3.6 Date: 04292011 Location(s):...

176

Decommissioning and Dismantling of the Floating Maintenance Base 'Lepse' - 13316  

SciTech Connect

The Lepse was built in Russia in 1934 and commissioned as a dry cargo ship. In 1961 she was re-equipped for use as a nuclear service ship (NSS), specifically a floating maintenance base (FMB), to support the operation of the civilian nuclear fleet (ice-breakers) of the USSR. In 1988 Lepse was taken out of service and in 1990 she was re-classified as a 'berth connected ship', located at a berth near the port of Murmansk under the ownership of Federal State Unitary Enterprise (FSUE) Atomflot. Lepse has special storage facilities for spent nuclear fuel assemblies (SFA) that have been used to store several hundred SFAs for nearly 40 years. High and intermediate-level liquid radioactive waste (LRW) is also present in the spent nuclear fuel assembly storage channels, in special tanks and also in the SFA cooling circuit. Many of the SFAs stored in Lepse are classified as damaged and cannot be removed using standard procedures. The removal of the SFA and LRW from the Lepse storage facilities is a hazardous task and requires specially designed tools, equipment and an infrastructure in which these can be deployed safely. Lepse is a significant environmental hazard in the North West of Russia. Storing spent nuclear fuel and high-level liquid radioactive waste on board Lepse in the current conditions is not acceptable with respect to Russian Federation health, safety and environmental standards and with international best practice. The approved concept design for the removal of the SFA and LRW and dismantling of Lepse requires that the ship be transported to Nerpa shipyard where specialist infrastructure will be constructed and equipment installed. One of the main complexities of the Project lies within the number of interested stakeholders involved in the Project. The Lepse project has been high focus on the international stage for many years with previous international efforts failing to make significant progress towards the objective of decommissioning Lepse. The Northern Dimension Environmental Partnership (NDEP) approved an internationally funded project to identify and prioritise nuclear and environmental hazards in NW Russia. Within this project the Lepse was recognised as being one of the highest nuclear hazards in NW Russia. Removal of SNF, SRW and LRW from Lepse requires innovative design and development of bespoke equipment. The main drivers of the NDEP Donors are first to safely transport Lepse in 2012 from her current berth close to the local population in Murmansk to the nominated dismantling shipyard, and secondly to raise Lepse from the water in 2013 onto the slip-way at the dismantling shipyard. A description is provided of the approach and progress towards preparing the Lepse for the removal of SFAs and other radioactive waste, to decontaminate and then dismantle the vessel under international donor funding. (authors)

Field, D.; Mizen, K. [Nuvia Limited (United Kingdom)] [Nuvia Limited (United Kingdom)

2013-07-01T23:59:59.000Z

177

Engineering and planning for decommissioning of nuclear power plants  

SciTech Connect

With the publication of NUREG-0586, ''Draft Generic Environmental Impact Statement on Decommissioning of Nuclear Facilities'' in January, 1981 the Nuclear Regulatory Commission staff has put the industry on notice that the termination of operating licenses and the final disposal of physical facilities will require the early consideration of several options and approaches and the preparation of comprehensive engineering and planning documents for the selected option at the end of useful life. This paper opens with a discussion of the options available and the principal aspects of decommissioning. The major emphasis of the composition is the nature of documents, the general approach to be followed, and special considerations to be taken into account when performing the detailed engineering and planning for decommissioning, as the end of life approaches and actual physical disposal is imminent. The author's main point of reference is on-going work by Burns and Roe, with Nuclear Energy Services, under contract to the Department of Energy's Richland Office, to perform the engineering and planning for the decommissioning of the Shippingport Atomic Power Station in Pennsylvania.

Gans, G.M. Jr.

1982-01-01T23:59:59.000Z

178

Conduction cooled tube supports  

DOE Patents (OSTI)

In boilers, process tubes are suspended by means of support studs that are in thermal contact with and attached to the metal roof casing of the boiler and the upper bend portions of the process tubes. The support studs are sufficiently short that when the boiler is in use, the support studs are cooled by conduction of heat to the process tubes and the roof casing thereby maintaining the temperature of the stud so that it does not exceed 1400.degree. F.

Worley, Arthur C. (Mt. Tabor, NJ); Becht, IV, Charles (Morristown, NJ)

1984-01-01T23:59:59.000Z

179

Wound tube heat exchanger  

DOE Patents (OSTI)

What is disclosed is a wound tube heat exchanger in which a plurality of tubes having flattened areas are held contiguous adjacent flattened areas of tubes by a plurality of windings to give a double walled heat exchanger. The plurality of windings serve as a plurality of effective force vectors holding the conduits contiguous heat conducting walls of another conduit and result in highly efficient heat transfer. The resulting heat exchange bundle is economical and can be coiled into the desired shape. Also disclosed are specific embodiments such as the one in which the tubes are expanded against their windings after being coiled to insure highly efficient heat transfer.

Ecker, Amir L. (Duncanville, TX)

1983-01-01T23:59:59.000Z

180

Coiled Tubing Safety Manual  

SciTech Connect

This document addresses safety concerns regarding the use of coiled tubing as it pertains to the preservation of personnel, environment and the wellbore.

Crow, W.

1999-04-06T23:59:59.000Z

Note: This page contains sample records for the topic "tube project decommissioning" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


181

PROJECT MANGEMENT PLAN EXAMPLES Project Execution Example  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Project Execution Example Project Execution Example Example 73 6.3 Project Approach The overall schedule strategy for the PFP project includes ongoing minimum safe activities, combined with stabilization of materials followed by materials disposition, and subsequent transition of the PFP complex to a decommissioned state. The PFP material stabilization baseline was developed using a functionally-based work WBS. The WBS defines all activities required to take each material stream from their current location/conditions through stabilization (as required), and disposition the stabilized material as solid waste for shipment to WIPP or as product material for shipment to SRS. Initially, workshops were held with subject matter experts, project managers, schedulers, and support personnel (experts in the

182

Testing, expanding and implementing pollution prevention tools for environmental restoration and decontamination and decommissioning  

SciTech Connect

Pollution Prevention (P2) programs and projects within the DOE Environmental Restoration (ER) and Decontamination and Decommissioning (D and D) Programs have been independently developed and implemented at various sites. As a result, unique, innovative solutions used at one site may not be known to other sites, and other sites may continue to duplicate efforts to develop and implement similar solutions. Several DOE Program offices have funded the development of tools to assist ER/D and D P2 projects. To realize the full value of these tools, they need to be evaluated and publicized to field sites. To address these needs and concerns, Sandia National Laboratory (SNL/NM), Los Alamos National Laboratory (LANL), and the Oak Ridge Field Office (DOE-OR) have teamed to pilot test DOE training and tracking tools; transfer common P2 analyses between sites, and evaluate and expand P2 tools and methodologies. The project is supported by FY 98 DOE Pollution Prevention Complex-Wide Project Funds. This paper presents the preliminary results for each of the following project modules: Training, Waste Tracking Pilot, Information Exchange, Evaluate P2 Tools for ER/D and D, Field Test of P2 Tools; and DOE Information Exchange.

Roybal, J.A. [Sandia National Lab., Albuquerque, NM (United States); McInroy, D. [Los Alamos National Lab., NM (United States); Watson, J. [GTS Duratek, Albuquerque, NM (United States); Mizner, J. [ICF Kaiser, Albuquerque, NM (United States)

1998-06-01T23:59:59.000Z

183

Final report of the decontamination and decommissioning of the BORAX-V facility turbine building  

SciTech Connect

The Boiling Water Reactor Experiment (BORAX)-V Facility Turbine Building Decontamination and Decommissioning (D&D) Project is described in this report. The BORAX series of five National Reactor Testing Station (NRTS) reactors pioneered intensive work on boiling water reactor (BWR) experiments conducted between 1953 and 1964. Facility characterization, decision analyses, and D&D plans for the turbine building were prepared from 1979 through 1990. D&D activities of the turbine building systems were initiated in November of 1988 and completed with the demolition and backfill of the concrete foundation in March 1992. Due to the low levels of radioactivity and the absence of loose contamination, the D&D activities were completed with no radiation exposure to the workers. The D&D activities were performed in a manner that no radiological health or safety hazard to the public or to personnel at the Idaho National Engineering Laboratory (INEL) remain.

Arave, A.E.; Rodman, G.R.

1992-12-01T23:59:59.000Z

184

Final report of the decontamination and decommissioning of the BORAX-V facility turbine building  

SciTech Connect

The Boiling Water Reactor Experiment (BORAX)-V Facility Turbine Building Decontamination and Decommissioning (D D) Project is described in this report. The BORAX series of five National Reactor Testing Station (NRTS) reactors pioneered intensive work on boiling water reactor (BWR) experiments conducted between 1953 and 1964. Facility characterization, decision analyses, and D D plans for the turbine building were prepared from 1979 through 1990. D D activities of the turbine building systems were initiated in November of 1988 and completed with the demolition and backfill of the concrete foundation in March 1992. Due to the low levels of radioactivity and the absence of loose contamination, the D D activities were completed with no radiation exposure to the workers. The D D activities were performed in a manner that no radiological health or safety hazard to the public or to personnel at the Idaho National Engineering Laboratory (INEL) remain.

Arave, A.E.; Rodman, G.R.

1992-12-01T23:59:59.000Z

185

Gated SIT vidicon streak tube  

SciTech Connect

A recently developed prototype streak tube designed to produce high gain and resolution by incorporating the streak and readout functions in one envelope thereby minimizing photon-to-change transformations and eliminating external coupling losses is presented. The tube is based upon a grid-gated Silicon-Intensified-Target Vidicon (SITV) with integral Focus Projection Scan (FPS) TV readout. Demagnifying electron optics (m=0.63) in the image section map the 40-mm-diameter photocathode image unto a 25-mm-diameter silicon target where gains greater than or equal to10/sup 3/ are achieved with only 10 KV accelerating voltage. This is compared with much lower gains (approx.50) at much higher voltages (approx.30 KV) reported for streak tubes using phosphor screens. Because SIT technology is well established means for electron imaging in vacuum, such fundamental problems as ''backside thinning'' required for electron imaging unto CCDs do not exist. The high spatial resolution (approx.30 lp/mm), variable scan formats, and high speed electrostatic deflection (250 mm/sup 2/ areas are routinely rastered with 256 scan lines in 1.6 ms) available from FPS readout add versatility not available in CCD devices. Theoretical gain and spatial resolution for this design (developed jointly by Los Alamos National Laboratory and General Electric Co.) are compared with similar calculations and measured data obtained for RCA 73435 streaks fiber optically coupled to (1) 25-mm-diameter SIT FPS vidicons and (2) 40-mm-diameter MCPTs (proximity-focused microchannel plate image intensifier tubes) fiber optically coupled to 18-mm-diameter Sb/sub 2/S/sub 3/ FPS vidicons. Sweep sensitivity, shutter ratio, and record lengths for nanosecond duration (20 to 200 ns) streak applications are discussed.

Dunbar, D.L.; Yates, G.J.; Black, J.P.

1985-01-01T23:59:59.000Z

186

Guided wave acoustic monitoring of corrosion in recovery boiler tubing  

SciTech Connect

Corrosion of tubing used in black-liquor recovery boilers is a major concern in all pulp and paper mills. Extensive corrosion in recovery boiler tubes can result in a significant safety and environmental hazard. Considerable plant resources are expended to inspect recovery boiler tubing. Currently, visual and ultrasonic inspections are primarily used during the annual maintenance shutdown to monitor corrosion rates and cracking of tubing. This Department of Energy, Office of Industrial Technologies project is developing guided acoustic waves for use on recovery boiler tubing. The feature of this acoustic technique is its cost-effectiveness in inspecting long lengths of tubes from a single inspection point. A piezoelectric or electromagnetic transducer induces guided waves into the tubes. The transducer detects fireside defects from the coldside or fireside of the tube. Cracking and thinning on recovery boiler tubes have been detected with this technique in both laboratory and field applications. This technique appears very promising for recovery boiler tube application, potentially expediting annual inspection of tube integrity.

Quarry, M J; Chinn, D J

2004-02-19T23:59:59.000Z

187

Boiler Stack Economizer Tube Failure  

Science Journals Connector (OSTI)

A metallurgical evaluation was performed to investigate the failure of a type 304 stainless steel tube from a boiler stack economizer. The tube had three distinct degradation mechanisms...

Ryan J. Haase; Larry D. Hanke

2013-10-01T23:59:59.000Z

188

Decontamination and decommissioning surveillance and maintenance report for FY 1991  

SciTech Connect

The Decontamination and Decommissioning (D D) Program has three distinct phases: (1) surveillance and maintenance (S M); (2) decontamination and removal of hazardous materials and equipment (which DOE Headquarters in Washington, D.C., calls Phase I of remediation); and (3) decommissioning and ultimate disposal, regulatory compliance monitoring, and property transfer (which DOE Headquarters calls Phase II of remediation). A large part of D D is devoted to S M at each of the sites. Our S M activities, which are performed on facilities awaiting decommissioning, are designed to minimize potential hazards to human health and the environment by: ensuring adequate containment of residual radioactive and hazardous materials; and, providing physical safety and security controls to minimize potential hazards to on-site personnel and the general public. Typically, we classify maintenance activities as either routine or special (major repairs). Routine maintenance includes such activities as painting, cleaning, vegetation control, minor structural repairs, filter changes, and building system(s) checks. Special maintenance includes Occupational Safety and Health Act facility upgrades, roof repairs, and equipment overhaul. Surveillance activities include inspections, radiological measurements, reporting, records maintenance, and security (as required) for controlling and monitoring access to facilities. This report summarizes out FY 1991 S M activities for the Tennessee plant sites, which include the K-25 Site, the Gas Centrifuge facilities, ORNL, and the Y-12 Plant.

Not Available

1991-12-01T23:59:59.000Z

189

Photomultiplier Tube Testing  

NLE Websites -- All DOE Office Websites (Extended Search)

Photomultiplier Tube Testing for the MiniBooNE Experiment B. T. Fleming, L. Bugel, E. Hawker, S. Koutsoliotas, S. McKenney, V. Sandberg, and D. Smith for the MiniBooNE...

190

Flameless tube sealing apparatus  

SciTech Connect

A flameless sealer for glass and polymeric tubes uses a circular filament as a heating element and can be used for sealing relatively large diameter tubes while they are within a glovebox or other protected enclosure. The electrically conductive rods extending from a non-conductive base which defines an aperture for mounting the apparatus to a lattice rod of a glove box. A remotely located power supply provides electrical power to the filament. 2 figs.

McFarlan, J.T.; Zwick, B.D.; Avens, L.R.

1991-03-04T23:59:59.000Z

191

Texture control of zircaloy tubing during tube reduction  

SciTech Connect

Seven batches of Zircaloy-2 nuclear fuel cladding tubes with different textures were processed from tube shells of the same size, by different reduction routes, using pilger and 3-roll mills. Based on the texture data of these tubes, the texture control of Zircaloy tubing, the texture gradient across the wall, and the texture change during annealing were studied. The deformation texture of Zicaloy-2 tubing was dependent on the tool's curvature and was independent of the dimensions of the mother tubes. The different slopes of texture gradients were observed between the tubing of higher strain ration and that of lower strain ratio.

Nagai, N.; Kakuma, T.; Fujita, K.

1982-01-01T23:59:59.000Z

192

A New Life Adaptive Reuse and Redevelopment of Decommissioned Commercial Nuclear Power Plants.  

E-Print Network (OSTI)

??My study analyzed the challenges and opportunities faced in the historic preservation and adaptive reuse of decommissioned commercial nuclear power plants. While operating, these plants… (more)

Farrow, Elizabeth

2008-01-01T23:59:59.000Z

193

EIS-0119: Decommissioning of Eight Surplus Production Reactors at the Harford Site, Richland, WA  

Energy.gov (U.S. Department of Energy (DOE))

This EIS presents analyses of potential environmental impacts of decommissioning the eight surplus production reactors at the Hanford Site near Richland, Washington.

194

Statement of Intent between the US Department of Energy and UK Nuclear Decommissioning Authority  

Energy.gov (U.S. Department of Energy (DOE))

Statement of Intent between the US Department of Energy and UK Nuclear Decommissioning Authority for exchange of information concerning management of radioactive waste.

195

EIS-0329: Proposed Construction, Operation, Decontamination/Decommissioning of Depleted Uranium Hexafluoride Conversion Facilities  

Energy.gov (U.S. Department of Energy (DOE))

This EIS analyzes DOE's proposal to construct, operate, maintain, and decontaminate and decommission two depleted uranium hexafluoride (DUF 6) conversion facilities, at Portsmouth, Ohio, and Paducah, Kentucky.

196

EIS-0119: Decommissioning of Eight Surplus Production Reactors at the Hanford Site, Richland, Washington  

Energy.gov (U.S. Department of Energy (DOE))

This EIS presents analyses of potential environmental impacts of decommissioning the eight surplus production reactors at the Hanford Site near Richland, Washington.

197

Technology, safety, and costs of decommissioning reference nuclear research and test reactors: sensitivity of decommissioning radiation exposure and costs to selected parameters  

SciTech Connect

Additional analyses of decommissioning at the reference research and test (R and T) reactors and analyses of five recent reactor decommissionings are made that examine some parameters not covered in the initial study report (NUREG/CR-1756). The parameters examined for decommissioning are: (1) the effect on costs and radiation exposure of plant size and/or type; (2) the effects on costs of increasing disposal charges and of unavailability of waste disposal capacity at licensed waste disposal facilities; and (3) the costs of and the available alternatives for the disposal of nuclear R and T reactor fuel assemblies.

Konzek, G.J.

1983-07-01T23:59:59.000Z

198

Erosion of heat exchanger tubes in fluidized beds  

SciTech Connect

This final report describes the activities of the 3-year project entitled Erosion of Heat Exchanger Tubes In Fluidized Beds.'' which was completed at the end of 1990. Project accomplishments include the collection of a substantial body of wear data In a 24in. [times] 24in. fluidized bed, comparative wear results In a 6in. [times] 6in. fluidized bed, the development of a dragometer and the collection of a comprehensive set of drag force data in the 24in. [times] 24in. bed, Fast Fourier Transform (FFT) analysis of bubble probe data to establish dominant bubble frequencies in the 24in. [times] 24in. bed, the use of a heat flux gauge for measurement of heat transfer coefficients in the 24in. [times] 24in. bed and the modeling of the tube wear in the 24in. [times] 24in. bed. Analysis of the wear data from the 24in. square bed indicates that tube wear increases with increase in superficial velocity, and with increase in tube height. The latter effect is a result of the tubes higher up in the bed seeing greater movement of dense phase than tubes lower down In the bed. In addition, tube wear was found to decrease with increase in particle size, for constant superficial velocity. Three models of tube wear were formulated and provided acceptable prediction of wear when compared with the experimental data.

Johnson, E.K.; Flemmer, R.L.C.

1991-01-01T23:59:59.000Z

199

Y-12 Plant Decontamination and Decommissioning Technology Logic Diagram for Building 9201-4. Volume 1: Technology evaluation  

SciTech Connect

During World War 11, the Oak Ridge Y-12 Plant was built as part of the Manhattan Project to supply enriched uranium for weapons production. In 1945, Building 9201-4 (Alpha-4) was originally used to house a uranium isotope separation process based on electromagnetic separation technology. With the startup of the Oak Ridge K-25 Site gaseous diffusion plant In 1947, Alpha-4 was placed on standby. In 1953, the uranium enrichment process was removed, and installation of equipment for the Colex process began. The Colex process--which uses a mercury solvent and lithium hydroxide as the lithium feed material-was shut down in 1962 and drained of process materials. Residual Quantities of mercury and lithium hydroxide have remained in the process equipment. Alpha-4 contains more than one-half million ft{sup 2} of floor area; 15,000 tons of process and electrical equipment; and 23,000 tons of insulation, mortar, brick, flooring, handrails, ducts, utilities, burnables, and sludge. Because much of this equipment and construction material is contaminated with elemental mercury, cleanup is necessary. The goal of the Y-12 Plant Decontamination and Decommissioning Technology Logic Diagram for Building 9201-4 is to provide a planning document that relates decontamination and decommissioning and waste management problems at the Alpha-4 building to the technologies that can be used to remediate these problems. The Y-12 Plant Decontamination and Decommissioning Technology Logic Diagram for Building 9201-4 builds on the methodology transferred by the U.S. Air Force to the Environmental Management organization with DOE and draws from previous technology logic diagram-efforts: logic diagrams for Hanford, the K-25 Site, and ORNL.

NONE

1994-09-01T23:59:59.000Z

200

DOE Environmental Management Strategy and Experience for In-Situ Decommissioning  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Strategy and Experience Strategy and Experience for In Situ Decommissioning Prepared By U.S. Department of Energy Office of Environmental Management Office of Engineering and Technology, EM-20 September 2009 This page is deliberately blank. DOE EM Strategy and Experience for In Situ Decommissioning i Contents Acknowledgements......................................................................................................................................iv Acronyms...................................................................................................................................................... v 1. Introduction......................................................................................................................................

Note: This page contains sample records for the topic "tube project decommissioning" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


201

EIS-0080: Decommissioning of the Shippingport Atomic Power Station, Hanford Site, Richland, Washington  

Energy.gov (U.S. Department of Energy (DOE))

The U.S. Department of Energy's Remedial Actions Program Office developed this statement to assess the impacts of decommissioning the Shippingport Atomic Power Station as well as analyze possible decommissioning alternatives, evaluate potential environmental impacts associated with each alternative, and present cost estimates for each alternative.

202

EIS-0080: Decommissioning of the Shipping port Atomic Power Station, Hanford Site, Richland, Washington  

Energy.gov (U.S. Department of Energy (DOE))

The U.S. Department of Energy's Remedial Actions Program Office developed this statement to assess the impacts of decommissioning the Shippingport Atomic Power Station as well as analyze possible decommissioning alternatives, evaluate potential environmental impacts associated with each alternative, and present cost estimates for each alternative.

203

Deactivation & Decommissioning Knowledge Management Information Tool (D&D  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Site & Facility Restoration » Deactivation & Site & Facility Restoration » Deactivation & Decommissioning (D&D) » Deactivation & Decommissioning Knowledge Management Information Tool (D&D KM-IT) Deactivation & Decommissioning Knowledge Management Information Tool (D&D KM-IT) Deactivation & Decommissioning Knowledge Management Information Tool (D&D KM-IT) The Deactivation and Decommissioning Knowledge Management Information Tool (D&D KM-IT) serves as a centralized repository providing a common interface for all D&D related activities. It assists users in gathering, analyzing, storing and sharing knowledge and information within the D&D community. This approach assists in reducing the need to rediscover the knowledge of the past while capturing the new knowledge and experiences gained during

204

Downhole pulse tube refrigerators  

SciTech Connect

This report summarizes a preliminary design study to explore the plausibility of using pulse tube refrigeration to cool instruments in a hot down-hole environment. The original motivation was to maintain Dave Reagor`s high-temperature superconducting electronics at 75 K, but the study has evolved to include three target design criteria: cooling at 30 C in a 300 C environment, cooling at 75 K in a 50 C environment, cooling at both 75 K and 30 C in a 250 C environment. These specific temperatures were chosen arbitrarily, as representative of what is possible. The primary goals are low cost, reliability, and small package diameter. Pulse-tube refrigeration is a rapidly growing sub-field of cryogenic refrigeration. The pulse tube refrigerator has recently become the simplest, cheapest, most rugged and reliable low-power cryocooler. The authors expect this technology will be applicable downhole because of the ratio of hot to cold temperatures (in absolute units, such as Kelvin) of interest in deep drilling is comparable to the ratios routinely achieved with cryogenic pulse-tube refrigerators.

Swift, G.; Gardner, D. [Los Alamos National Lab., NM (United States). Condensed Matter and Thermal Physics Group

1997-12-01T23:59:59.000Z

205

Fluorescent Tube Lamps  

Energy.gov (U.S. Department of Energy (DOE))

FEMP temporarily suspended its energy efficiency requirements for fluorescent tube lamps as it evaluates the market impact of the pending 2012 minimum efficiency standards for fluorescent lamps. The program will issue updated energy efficiency requirements when the market distribution of this product category stabilizes and when doing so has the potential to result in significant Federal energy savings.

206

Resource book: Decommissioning of contaminated facilities at Hanford  

SciTech Connect

In 1942 Hanford was commissioned as a site for the production of weapons-grade plutonium. The years since have seen the construction and operation of several generations of plutonium-producing reactors, plants for the chemical processing of irradiated fuel elements, plutonium and uranium processing and fabrication plants, and other facilities. There has also been a diversification of the Hanford site with the building of new laboratories, a fission product encapsulation plant, improved high-level waste management facilities, the Fast Flux test facility, commercial power reactors and commercial solid waste disposal facilities. Obsolescence and changing requirements will result in the deactivation or retirement of buildings, waste storage tanks, waste burial grounds and liquid waste disposal sites which have become contaminated with varying levels of radionuclides. This manual was established as a written repository of information pertinent to decommissioning planning and operations at Hanford. The Resource Book contains, in several volumes, descriptive information of the Hanford Site and general discussions of several classes of contaminated facilities found at Hanford. Supplementing these discussions are appendices containing data sheets on individual contaminated facilities and sites at Hanford. Twelve appendices are provided, corresponding to the twelve classes into which the contaminated facilities at Hanford have been organized. Within each appendix are individual data sheets containing administrative, geographical, physical, radiological, functional and decommissioning information on each facility within the class. 68 refs., 54 figs., 18 tabs.

Not Available

1991-09-01T23:59:59.000Z

207

Y-12 Plant decontamination and decommissioning technology logic diagram for Building 9201-4. Volume 2: Technology logic diagram  

SciTech Connect

The Y-12 Plant Decontamination and Decommissioning Technology Logic Diagram for Building 9201-4 (TLD) was developed to provide a decision-support tool that relates decontamination and decommissioning (D and D) problems at Bldg. 9201-4 to potential technologies that can remediate these problems. This TLD identifies the research, development, demonstration, testing, and evaluation needed for sufficient development of these technologies to allow for technology transfer and application to D and D and waste management (WM) activities. It is essential that follow-on engineering studies be conducted to build on the output of this project. These studies will begin by selecting the most promising technologies identified in the TLD and by finding an optimum mix of technologies that will provide a socially acceptable balance between cost and risk. The TLD consists of three fundamentally separate volumes: Vol. 1 (Technology Evaluation), Vol. 2 (Technology Logic Diagram), and Vol. 3 (Technology Evaluation Data Sheets). Volume 2 contains the logic linkages among environmental management goals, environmental problems, and the various technologies that have the potential to solve these problems. Volume 2 has been divided into five sections: Characterization, Decontamination, Dismantlement, Robotics/Automation, and Waste Management. Each section contains logical breakdowns of the Y-12 D and D problems by subject area and identifies technologies that can be reasonably applied to each D and D challenge.

NONE

1994-09-01T23:59:59.000Z

208

Y-12 Plant decontamination and decommissioning technology logic diagram for Building 9201-4: Volume 2, Technology Logic Diagram  

SciTech Connect

The Y-12 Plant Decontamination and Decommissioning Technology Logic Diagram for Building 9201-4 (TLD) was developed to provide a decision-support tool that relates decontamination and decommissioning (D&D) problems at 9201-4 to potential technologies that can remediate these problems. The TLD uses information from the Strategic Roadmap for the Oak Ridge Reservation, the Oak K-25 Site technology Logic Diagram, and Oak Ridge National Laboratory Technology Logic Diagram, and a previous Hanford logic diagram. This TLD identifies the research, development, demonstration, testing, and evaluation needed for sufficient development of these technologies to allow for technology transfer and application to D&D and waste management activities. It is essential that follow-on engineering studies be conducted to build on the output of this project. These studies will begin by selecting the most promising technologies identified in the TLD and by finding an optimum mix of technologies that will provide a socially acceptable balance between the cost and risk. The TLD consists of three volumes. Volume 1 presents an overview of the TLD, an explanation of the program-specific responsibilities, a review of identified technologies, and the rankings of remedial technologies. Volume 2 contains the logic linkages among the environmental management goals, environmental problems, and the various technologies that have the potential to solve these problems. Volume 3 contains the TLD data sheets.

NONE

1994-09-01T23:59:59.000Z

209

Decontamination and decommissioning of the Chemical Process Cell (CPC): Topical report for the period January 1985-March 1987  

SciTech Connect

To support interim storage of vitrified High-Level Waste (HLW) at the West Valley Demonstration Project, the shielded, remotely operated Chemical Process Cell (CPC) was decommissioned and decontaminated. All equipment was removed, packaged and stored for future size reduction and decontamination. Floor debris was sampled, characterized, and vacuumed into remotely handled containers. The cell walls, ceiling, and floor were decontaminated. Three 20 Mg (22.5 ton) concrete neutron absorber cores were cut with a high-pressure water/abrasive jet cutting system and packaged for disposal. All operations were performed remotely using two overhead bridge cranes which included two 1.8 Mg (2 ton) hoists, one 14.5 Mg (16 ton) hoist, and an electromechanical manipulator or an industrial robot mounted on a mobile platform. Initial general area dose rates in the cell ranged from 1 to 50 R/h. Target levels of less than 10 mR/h general area readings were established before decontamination and decommissioning was initiated; general area dose rates between 200 mR/h and 1200 mR/h were obtained at the completion of the decontamination work. 4 refs., 11 figs., 8 tabs.

Meigs, R. A.

1987-07-01T23:59:59.000Z

210

Condensation in horizontal heat exchanger tubes  

SciTech Connect

Many innovative reactor concepts for Generation III nuclear power plants use passive safety equipment for residual heat removal. These systems use two phase natural circulation. Heat transfer to the coolant results in a density difference providing the driving head for the required mass flow. By balancing the pressure drop the system finds its operational mode. Therefore the systems depend on a strong link between heat transfer and pressure drop determining the mass flow through the system. In order to be able to analyze these kind of systems with the help of state of the art computer codes the implemented numerical models for heat transfer, pressure drop or two phase flow structure must be able to predict the system performance in a wide parameter range. Goal of the program is to optimize the numerical models and therefore the performance of computer codes analyzing passive systems. Within the project the heat transfer capacity of a heat exchanger tube will be investigated. Therefore the tube will be equipped with detectors, both temperature and pressure, in several directions perpendicular to the tube axis to be able to resolve the angular heat transfer. In parallel the flow structure of a two phase flow inside and along the tube will be detected with the help of x-ray tomography. The water cooling outside of the tube will be realized by forced convection. It will be possible to combine the flow structure measurement with an angular resolved heat transfer for a wide parameter range. The test rig is set up at the TOPLFOW facility at the Helmholtz-Zentrum Dresden-Rossendorf (HZDR), so that it will be possible to vary the pressure between 5 and 70 bar. The steam mass content will be varied between 0 and 100 percent. The results will be compared to the large scaled Emergency Condenser Tests performed at the INKA test facility in Karlstein (Germany). The paper will explain the test setup and the status of the project will be presented. (authors)

Leyer, S.; Zacharias, T.; Maisberger, F.; Lamm, M. [AREVA NP GmbH, Paul-Gossen-Strasse 100, Erlangen, 91052 (Germany); Vallee, C.; Beyer, M.; Hampel, U. [Helmholtz-Zentrum Dresden-Rossendorf e.V., Bautzner Landstrasse 400, Dresden, 01328 (Germany)

2012-07-01T23:59:59.000Z

211

Technology, Safety and Costs of Decommissioning Nuclear Reactors At Multiple-Reactor Stations  

SciTech Connect

Safety and cost information is developed for the conceptual decommissioning of large (1175-MWe) pressurized water reactors (PWRs) and large (1155-MWe) boiling water reactors {BWRs) at multiple-reactor stations. Three decommissioning alternatives are studied: DECON (immediate decontamination), SAFSTOR (safe storage followed by deferred decontamination), and ENTOMB (entombment). Safety and costs of decommissioning are estimated by determining the impact of probable features of multiple-reactor-station operation that are considered to be unavailable at a single-reactor station, and applying these estimated impacts to the decommissioning costs and radiation doses estimated in previous PWR and BWR decommissioning studies. The multiple-reactor-station features analyzed are: the use of interim onsite nuclear waste storage with later removal to an offsite nuclear waste disposal facility, the use of permanent onsite nuclear waste disposal, the dedication of the site to nuclear power generation, and the provision of centralized services. Five scenarios for decommissioning reactors at a multiple-reactor station are investigated. The number of reactors on a site is assumed to be either four or ten; nuclear waste disposal is varied between immediate offsite disposal, interim onsite storage, and immediate onsite disposal. It is assumed that the decommissioned reactors are not replaced in one scenario but are replaced in the other scenarios. Centralized service facilities are provided in two scenarios but are not provided in the other three. Decommissioning of a PWR or a BWR at a multiple-reactor station probably will be less costly and result in lower radiation doses than decommissioning an identical reactor at a single-reactor station. Regardless of whether the light water reactor being decommissioned is at a single- or multiple-reactor station: • the estimated occupational radiation dose for decommissioning an LWR is lowest for SAFSTOR and highest for DECON • the estimated cost of decommissioning a PWR is lowest for ENTOMB and highest for SAFSTOR • the estimated cost of decommissioning a BWR is lowest for OECON and highest for SAFSTOR. In all cases, SAFSTOR has the lowest occupational radiation dose and the highest cost.

Wittenbrock, N. G.

1982-01-01T23:59:59.000Z

212

Joined concentric tubes  

DOE Patents (OSTI)

Tubular objects having two or more concentric layers that have different properties are joined to one another during their manufacture primarily by compressive and friction forces generated by shrinkage during sintering and possibly mechanical interlocking. It is not necessary for the concentric tubes to display adhesive-, chemical- or sinter-bonding to each other in order to achieve a strong bond. This facilitates joining of dissimilar materials, such as ceramics and metals.

DeJonghe, Lutgard; Jacobson, Craig; Tucker, Michael; Visco, Steven

2013-01-01T23:59:59.000Z

213

Single-tube thermal and hydraulic tube support test. Volume 2. Appendixes. Final report  

SciTech Connect

The work described in this report (volumes 1 and 2) was an experimental project to measure the inception and extent of dryout or liquid deficient heat transfer and chemical precipitation in presently used steam generator tube-tube support geometries and modified geometries. Since chemical precipitation or concentration may lead to corrosion, this program was planned to find the dependence of dryout and chemical precipitation on geometry, heat flux and fluid conditions. It was found that dryout depended principally on tube support geometry and heat flux. There was little dependence on flow rate, quality and pressure. It was found that certain tube support geometries could produce local dryout which in turn could permit significant chemical concentration. Chemical concentration was not found in the tube support geometries not exhibiting dryout. The interrelationship between the heat and mass transfer processes in the crevices was further demonstrated by comparing the results of an analytic model for predicting the shape of the liquid-vapor interface to the outline of a precipitate pattern resulting from chemical concentration.

Curlee, N.J. Jr.; Baum, A.J.

1981-09-01T23:59:59.000Z

214

Single-tube thermal and hydraulic tube support test. Final report  

SciTech Connect

The work described in this report (volumes 1 and 2) was an experimental project to measure the inception and extent of dryout or liquid deficient heat transfer and chemical precipitation in presently used steam generator tube-tube support geometries and modified geometries. Since chemical precipitation or concentration may lead to corrosion this program was planned to find the dependence of dryout and chemical precipitation on geometry, heat flux and fluid conditions. It was found that dryout depended principally on tube support geometry and heat flux. There was little dependence on flow rate, quality and pressure. It was found that certain tube support geometries could produce local dryout which in turn could permit significant chemical concentration. Chemical concentration was not found in tube support geometries not exhibiting dryout. The interrelationship between the heat and mass transfer processes in the crevices was further demonstrated by comparing the results of an analytic model for predicting the shape of the liquid vapor interface to the outline of a precipitate pattern resulting from chemical concentration.

Curlee, N.J. Jr.; Baum, A.J.

1981-09-01T23:59:59.000Z

215

Sensor Network Demonstration for In Situ Decommissioning - 13332  

SciTech Connect

Florida International University's (FIU's) Applied Research Center is currently supporting the Department of Energy's (DOE) Environmental Management Office of D and D and Facility Engineering program. FIU is supporting DOE's initiative to improve safety, reduce technical risks, and limit uncertainty within D and D operations by identifying technologies suitable to meet specific facility D and D requirements, assessing the readiness of those technologies for field deployment, and conducting feasibility studies and large scale demonstrations of promising technologies. During FY11, FIU collaborated with Savannah River National Laboratory in the development of an experimental test site for the demonstration of multiple sensor systems for potential use in the in situ decommissioning process. In situ decommissioning is a process in which the above ground portion of a facility is dismantled and removed, and the underground portion is filled with a cementious material such as grout. In such a scenario, the question remains on how to effectively monitor the structural health of the grout (cracking, flexing, and sinking), as well as track possible migration of contaminants within and out of the grouted monolith. The right types of sensors can aid personnel in better understanding the conditions within the entombed structure. Without sensors embedded in and around the monolith, it will be very difficult to estimate structural integrity and contaminant transport. Yet, to fully utilize the appropriate sensors and the provided data, their performance and reliability must be evaluated outside a laboratory setting. To this end, a large scale experimental setup and demonstration was conducted at FIU. In order to evaluate a large suite of sensor systems, FIU personnel designed and purchased a pre-cast concrete open-top cube, which served as a mock-up of an in situ DOE decommissioned facility. The inside of the cube measures 10 ft x 10 ft x 8 ft. In order to ensure that the individual sensors would be immobilized during the grout pouring activities, a set of nine sensor racks were designed. The 270 sensors provided by Idaho National Laboratory (INL), Mississippi State University (MSU), University of Houston (UH), and University of South Carolina (USC) were secured to these racks based on predetermined locations. Once sensor racks were installed inside the test cube, connected and debugged, approximately 32 cubic yards of special grout material was used to entomb the sensors. MSU provided and demonstrated four types of fiber loop ring-down (FLR) sensors for detection of water, temperature, cracks, and movement of fluids. INL provided and demonstrated time differenced 3D electrical resistivity tomography (ERT), advanced tensiometers for moisture content, and thermocouples for temperature measurements. University of Houston provided smart aggregate (SA) sensors, which detect crack severity and water presence. An additional UH sensor system demonstrated was a Fiber Bragg Grating (FBG) fiber optic system measuring strain, presence of water, and temperature. USC provided a system which measured acoustic emissions during cracking, as well as temperature and pH sensors. All systems were connected to a Sensor Remote Access System (SRAS) data networking and collection system designed, developed and provided by FIU. The purpose of SRAS was to collect and allow download of the raw sensor data from all the sensor system, as well as allow upload of the processed data and any analysis reports and graphs. All this information was made available to the research teams via the Deactivation and Decommissioning Knowledge Management and Information Tool (D and D KM-IT). As a current research effort, FIU is performing an energy analysis, and transferring several sensor systems to a Photovoltaic (PV) System to continuously monitor energy consumption parameters and overall power demands. Also, One final component of this research is focusing on developing an integrated data network to capture, log and analyze sensor system data in near real time from a single inte

Lagos, L.; Varona, J.; Awwad, A. [Applied Research Center, Florida International University, 10555 West Flagler Street, Suite 2100, Miami, FL 33174 (United States)] [Applied Research Center, Florida International University, 10555 West Flagler Street, Suite 2100, Miami, FL 33174 (United States); Rivera, J.; McGill, J. [Department of Energy - DOE, Environmental Management Office (United States)] [Department of Energy - DOE, Environmental Management Office (United States)

2013-07-01T23:59:59.000Z

216

Decontamination and decommissioning assessment for the Waste Incineration Facility (Building 232-Z) Hanford Site, [Hanford], WA  

SciTech Connect

Building 232-Z is an element of the Plutonium Finishing Plant (PFP) located in the 200 West Area of the Hanford Site. From 1961 until 1972, plutonium-bearing combustible materials were incinerated in the building. Between 1972 and 1983, following shutdown of the incinerator, the facility was used for waste segregation activities. The facility was placed in retired inactive status in 1984 and classified as a Limited Control Facility pursuant to DOE Order 5480.5, Safety of Nuclear Facilities, and 6430.1A, General Design Criteria. The current plutonium inventory within the building is estimated to be approximately 848 grams, the majority of which is retained within the process hood ventilation system. As a contaminated retired facility, Building 232-Z is included in the DOE Surplus Facility Management Program. The objective of this Decontamination and Decommissioning (D&D) assessment is to remove Building 232-Z, thereby elmininating the radiological and environmental hazards associated with the plutonium inventory within the structure. The steps to accomplish the plan objectives are: (1) identifying the locations of the most significant amounts of plutonium, (2) removing residual plutonium, (3) removing and decontaminating remaining building equipment, (4) dismantling the remaining structure, and (5) closing out the project.

Dean, L.N. [Advanced Sciences, Inc., (United States)

1994-02-01T23:59:59.000Z

217

Shock Tube Design  

E-Print Network (OSTI)

. The driver section drives the shock-front because of high pressured driving fluid contained in it. It contains the diaphragm holders, and the mechanisms that control their rupture along with an end cap. The driven section is the portion of the tube where... and to withstand higher pressures. The driver sections named driver-1 and driver-2 are shown in Figure 1. 10 Figure 1. Section view of the driver section. The end cap on the rear driver section is made of thicker material than the side walls because...

Koppenberger, Peter K.

2010-07-14T23:59:59.000Z

218

EA-1889: Disposal of Decommissioned, Defueled Naval Reactor Plants from USS  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

89: Disposal of Decommissioned, Defueled Naval Reactor Plants 89: Disposal of Decommissioned, Defueled Naval Reactor Plants from USS Enterprise (CVN 65) at the Hanford Site, Richland, Washington EA-1889: Disposal of Decommissioned, Defueled Naval Reactor Plants from USS Enterprise (CVN 65) at the Hanford Site, Richland, Washington Summary This EA, prepared by the Department of the Navy, evaluates the environmental impacts of the disposal of decommissioned, defueled, naval reactor plants from the USS Enterprise at DOE's Hanford Site, Richland, Washington. DOE participated as a cooperating agency in the preparation of this EA. The Department of the Navy issued its FONSI on August 23, 2012. Public Comment Opportunities No public comment opportunities available at this time. Documents Available for Download August 23, 2012

219

Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 13: Part 2, Indexes  

SciTech Connect

This is part 2 of a bibliography on nuclear facility decommissioning and site remedial action. This report contains indexes on the following: authors, corporate affiliation, title words, publication description, geographic location, subject category, and key word.

Goins, L.F.; Webb, J.R.; Cravens, C.D.; Mallory, P.K.

1992-09-01T23:59:59.000Z

220

Technology, Safety and Costs of Decommissioning a Reference Uranium Hexafluoride Conversion Plant  

SciTech Connect

Safety and cost information is developed for the conceptual decommissioning of a commercial uranium hexafluoride conversion (UF{sub 6}) plant. Two basic decommissioning alternatives are studied to obtain comparisons between cost and safety impacts: DECON, and passive SAFSTOR. A third alternative, DECON of the plant and equipment with stabilization and long-term care of lagoon wastes. is also examined. DECON includes the immediate removal (following plant shutdown) of all radioactivity in excess of unrestricted release levels, with subsequent release of the site for public use. Passive SAFSTOR requires decontamination, preparation, maintenance, and surveillance for a period of time after shutdown, followed by deferred decontamination and unrestricted release. DECON with stabilization and long-term care of lagoon wastes (process wastes generated at the reference plant and stored onsite during plant operation} is also considered as a decommissioning method, although its acceptability has not yet been determined by the NRC. The decommissioning methods assumed for use in each decommissioning alternative are based on state-of-the-art technology. The elapsed time following plant shutdown required to perform the decommissioning work in each alternative is estimated to be: for DECON, 8 months; for passive SAFSTOR, 3 months to prepare the plant for safe storage and 8 months to accomplish deferred decontamination. Planning and preparation for decommissioning prior to plant shutdown is estimated to require about 6 months for either DECON or passive SAFSTOR. Planning and preparation prior to starting deferred decontamination is estimated to require an additional 6 months. OECON with lagoon waste stabilization is estimated to take 6 months for planning and about 8 months to perform the decommissioning work. Decommissioning cost, in 1981 dollars, is estimated to be $5.91 million for OECON. For passive SAFSTOR, preparing the facility for safe storage is estimated to cost $0.88 million, the annual maintenance and surveillance cost is estimated to be about $0.095 million, and deferred decontamination is estimated to cost about $6.50 million. Therefore, passive SAFSTOR for 10 years is estimated to cost $8.33 million in nondiscounted 1981 dollars. DECON with lagoon waste stabilization is estimated to cost about $4.59 million, with an annual cost of $0.011 million for long-term care. All of these estimates include a 25% contingency. Waste management costs for DECON, including the net cost of disposal of the solvent extraction lagoon wastes by shipping those wastes to a uranium mill for recovery of residual uranium, comprise about 38% of the total decommissioning cost. Disposal of lagoon waste at a commercial low-level waste burial ground is estimated to add $10.01 million to decommissioning costs. Safety analyses indicate that radiological and nonradiological safety impacts from decommissioning activities should be small. The 50-year committed dose equivalent to members of the public from airborne releases during normal decommissioning activities is estimated to 'Je about 4.0 man-rem. Radiation doses to the public from accidents are found to be very low for all phases of decommissioning. Occupational radiation doses from normal decommissioning operations (excluding transport operations) are estimated to be about 79 man-rem for DECON and about 80 man-rem for passive SAFSTOR with 10 years of safe storage. Doses from DECON with lagoon waste stabilization are about the same as for DECON except there is less dose resulting from transportation of radioactive waste. The number of fatalities and serious lost-time injuries not related to radiation is found to be very small for all decommissioning alternatives. Comparison of the cost estimates shows that DECON with lagoon waste stabilization is the least expensive method. However, this alternative does not allow unrestricted release of the site. The cumulative cost of maintenance and surveillance and the higher cost of deferred decontamination makes passive SAFSTOR more expensive than DECON. Seve

Elder, H. K.

1981-10-01T23:59:59.000Z

Note: This page contains sample records for the topic "tube project decommissioning" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


221

Statement of Intent No. 2 between DOE and the Nuclear Decommissioning Authority  

Energy.gov (U.S. Department of Energy (DOE))

Statement of Intent No. 2 between DOE and the Nuclear Decommissioning Authority in the United Kingdom of Great Britain and Northern Ireland for exchange of information concerning management of...

222

Savannah River Site Removes Dome, Opening Reactor for Recovery Act Decommissioning  

Energy.gov (U.S. Department of Energy (DOE))

American Recovery and Reinvestment Act workers achieved a significant milestone in the decommissioning of a Cold War reactor at the Savannah River Site this month after they safely removed its...

223

Statement of Intent NO. 2 between the US Department of Energy and UK Nuclear Decommissioning Authority  

Energy.gov (U.S. Department of Energy (DOE))

Statement of Intent NO. 2 between the Department of Energy of the United States and the Nuclear Decommissioning Authority in the United Kingdom of Great Britain and northern Ireland for exchange of...

224

Five-Year Technology Development Strategic Plan Targets EM’s Decommissioning Challenges  

Energy.gov (U.S. Department of Energy (DOE))

WASHINGTON, D.C. – Leaders from EM headquarters and field offices and the UK’s Sellafield nuclear site gathered recently to discuss developing technologies needed to address decommissioning challenges across the Cold War cleanup program.

225

Development of a Remote Monitoring Sensor Network for In-Situ Decommissioned Structures  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

10-01666, Revision 0 10-01666, Revision 0 Key Words: in situ decommissioning sensor remote monitoring end state Retention: Permanent DEVELOPMENT OF A REMOTE MONITORING SENSOR NETWORK FOR IN SITU DECOMMISSIONED STRUCTURES Panel Report November 2010 Savannah River National Laboratory Savannah River Nuclear Solutions Aiken, SC 29808 Prepared for the U.S. Department of Energy Under Contract Number DE-AC09-08SR22470 Development of a Remote Monitoring Sensor Network Page 2 of 34

226

Technology, safety, and costs of decommissioning reference nuclear research and test reactors. Main report  

SciTech Connect

Safety and Cost Information is developed for the conceptual decommissioning of two representative licensed nuclear research and test reactors. Three decommissioning alternatives are studied to obtain comparisons between costs (in 1981 dollars), occupational radiation doses, potential radiation dose to the public, and other safety impacts. The alternatives considered are: DECON (immediate decontamination), SAFSTOR (safe storage followed by deferred decontamination), and ENTOMB (entombment). The study results are presented in two volumes. Volume 1 (Main Report) contains the results in summary form.

Konzek, G.J.; Ludwick, J.D.; Kennedy, W.E. Jr.; Smith, R.I.

1982-03-01T23:59:59.000Z

227

Engineering Evaluation/Cost Analysis for Decommissioning of the Engineering Test Reactor Complex  

SciTech Connect

Preparation of this Engineering Evaluation/Cost Analysis is consistent with the joint U.S. Department of Energy and U.S. Environmental Protection Agency Policy on Decommissioning of Department of Energy Facilities Under the Comprehensive Environmental Response, Compensation, and Liability Act, which establishes the Comprehensive Environmental Response, Compensation, and Liability Act non-time-critical removal action (NTCRA) process as an approach for decommissioning.

A. B. Culp

2006-10-01T23:59:59.000Z

228

An analysis of decommissioning costs for the AFRRI TRIGA reactor facility  

SciTech Connect

A decommissioning cost analysis for the AFRRI TRIGA Reactor Facility was made. AFRRI is not at this time suggesting that the AFRRI TRIGA Reactor Facility be decommissioned. This report was prepared to be in compliance with paragraph 50.33 of Title 10, Code of Federal Regulations which requires the assurance of availability of future decommissioning funding. The planned method of decommissioning is the immediate decontamination of the AFRRI TRIGA Reactor site to allow for restoration of the site to full public access - this is called DECON. The cost of DECON for the AFRRI TRIGA Reactor Facility in 1990 dollars is estimated to be $3,200,000. The anticipated ancillary costs of facility site demobilization and spent fuel shipment is an additional $600,000. Thus the total cost of terminating reactor operations at AFRRI will be about $3,800,000. The primary basis for this cost estimate is a study of the decommissioning costs of a similar reactor facility that was performed by Battelle Pacific Northwest Laboratory (PNL) as provided in USNRC publication NUREG/CR-1756. The data in this study were adapted to reflect the decommissioning requirements of the AFRRI TRIGA. (author)

Forsbacka, Matt [Armed Forces Radiobiology Research Institute, Bethesda, MD (United States)

1990-07-01T23:59:59.000Z

229

Comparative Evaluation of Cutting Methods of Activated Concrete from Nuclear Power Plant Decommissioning - 13548  

SciTech Connect

The amount of radioactive wastes from decommissioning of a nuclear power plant varies greatly depending on factors such as type and size of the plant, operation history, decommissioning options, and waste treatment and volume reduction methods. There are many methods to decrease the amount of decommissioning radioactive wastes including minimization of waste generation, waste reclassification through decontamination and cutting methods to remove the contaminated areas. According to OECD/NEA, it is known that the radioactive waste treatment and disposal cost accounts for about 40 percentage of the total decommissioning cost. In Korea, it is needed to reduce amount of decommissioning radioactive waste due to high disposal cost, about $7,000 (as of 2010) per a 200 liter drum for the low- and intermediate-level radioactive waste (LILW). In this paper, cutting methods to minimize the radioactive waste of activated concrete were investigated and associated decommissioning cost impact was assessed. The cutting methods considered are cylindrical and volume reductive cuttings. The study showed that the volume reductive cutting is more cost-effective than the cylindrical cutting. Therefore, the volume reductive cutting method can be effectively applied to the activated bio-shield concrete. (authors)

Kim, HakSoo; Chung, SungHwan; Maeng, SungJun [Central Research Institute, Korea Hydro and Nuclear Power Co. Ltd., 1312-70 Yuseong-daero, Yuseong-gu, Daejeon 305-343 (Korea, Republic of)] [Central Research Institute, Korea Hydro and Nuclear Power Co. Ltd., 1312-70 Yuseong-daero, Yuseong-gu, Daejeon 305-343 (Korea, Republic of)

2013-07-01T23:59:59.000Z

230

Analysis of cracking of co-extruded recovery boiler floor tubes  

SciTech Connect

Cracking of the stainless steel layer in co-extruded 304L/SA210 tubing used in black liquor recovery boilers is being found in an ever-increasing number of North American pulp and paper mills. Because of the possibility of a tube failure, this is a significant safety issue, and, because of the extra time required for tube inspection and repair, this can become an economic issue as well. In a project funded by the U.S. Department of Energy and given wide support among paper companies, boiler manufacturers, and tube fabricators, studies are being conducted to determine the cause of the cracking and to identify alternate materials and/or operating procedures to prevent tube cracking. Examination of cracked tubes has permitted characterization of crack features, and transmission electron microscopy is providing information about the thermal history, particularly cyclic thermal exposures, that tubes have experienced. Neutron and x-ray diffraction techniques are being used to determine the residual stresses in as-fabricated tube panels and exposed tubes, and finite element modeling is providing information about the stresses the tubes experience during operation. Laboratory studies are being conducted to determine the susceptibility of the co-extruded 304L/SA210 tubes to stress corrosion cracking, thermal fatigue, and corrosion in molten smelt. This paper presents the current status of these studies. On the basis of all of these studies, recommendations for means to prevent tube cracking will be offered.

Keiser, J.R.; Taljat, B.; Wang, X.L. [and others

1997-08-01T23:59:59.000Z

231

Ion plated electronic tube device  

DOE Patents (OSTI)

An electronic tube and associated circuitry which is produced by ion plating techniques. The process is carried out in an automated process whereby both active and passive devices are produced at very low cost. The circuitry is extremely reliable and is capable of functioning in both high radiation and high temperature environments. The size of the electronic tubes produced are more than an order of magnitude smaller than conventional electronic tubes.

Meek, T.T.

1983-10-18T23:59:59.000Z

232

Technology, safety and costs of decommissioning a Reference Boiling Water Reactor Power Station. Main report. Volume 1  

SciTech Connect

Technology, safety and cost information is given for the conceptual decommissioning of a large (1100MWe) boiling water reactor (BWR) power station. Three approaches to decommissioning, immediate dismantlement, safe storage with deferred dismantlement and entombment, were studied to obtain comparisons between costs, occupational radiation doses, potential dose to the public and other safety impacts. It also shows the sensitivity of decommissioning safety and costs to the power rating of a BWR in the range of 200 to 1100 MWe.

Oak, H.D.; Holter, G.M.; Kennedy, W.E. Jr.; Konzek, G.J.

1980-06-01T23:59:59.000Z

233

Oak Ridge National Laboratory Technology Logic Diagram. Volume 2, Technology Logic Diagram: Part A, Decontamination and Decommissioning  

SciTech Connect

This report documents activities of decontamination and decommissioning at ORNL. Topics discussed include general problems, waste types, containment, robotics automation and decontamination processes.

Not Available

1993-09-01T23:59:59.000Z

234

SINGLE CRYSTAL NIOBIUM TUBES FOR PARTICLE COLLIDERS ACCELERATOR CAVITIES  

SciTech Connect

The objective of this research project is to produce single crystal niobium (Nb) tubes for use as particle accelerator cavities for the Fermi laboratory’s International Linear Collider project. Single crystal Nb tubes may have superior performance compared to a polycrystalline tubes because the absence of grain boundaries may permit the use of higher accelerating voltages. In addition, Nb tubes that are subjected to the high temperature, high vacuum crystallization process are very pure and well annealed. Any impurity with a significantly higher vapor pressure than Nb should be decreased by the relatively long exposure at high temperature to the high vacuum environment. After application of the single crystal process, the surfaces of the Nb tubes are bright and shiny, and the tube resembles an electro polished Nb tube. For these reasons, there is interest in single crystal Nb tubes and in a process that will produce single crystal tubes. To convert a polycrystalline niobium tube into a single crystal, the tube is heated to within a few hundred ?C of the melting temperature of niobium, which is 2477 ?C. RF heating is used to rapidly heat the tube in a narrow zone and after reaching the operating temperature, the hot zone is slowly passed along the length of the tube. For crystallization tests with Nb tubes, the traverse rate was in the range of 1-10 cm per hour. All the crystallization tests in this study were performed in a water-cooled, stainless steel chamber under a vacuum of 5 x10-6 torr or better. In earliest tests of the single crystal growth process, the Nb tubes had an OD of 1.9 cm and a wall thickness of 0.15 mm. With these relatively small Nb tubes, the single crystal process was always successful in producing single crystal tubes. In these early tests, the operating temperature was normally maintained at 2200 ?C, and the traverse rate was 5 cm per hour. In the next test series, the Nb tube size was increased to 3.8 cm OD and the wall thickness was increased 0.18 mm and eventually to 0.21 mm. Again, with these larger tubes, single crystal tubes were usually produced by the crystallization process. The power supply was generally operated at full output during these tests, and the traverse rate was 5 cm per hour. In a few tests, the traverse rate was increased to 10 cm per hour, and at the faster traverse rate, single crystal growth was not achieved. In these tests with a faster traverse rate, it was thought that the tube was not heated to a high enough temperature to achieve single crystal growth. In the next series of tests, the tube OD was unchanged at 3.8 cm and the wall thickness was increased to 0.30 mm. The increased wall thickness made it difficult to reach an operating temperature above 2,000 ?C, and although the single crystal process caused a large increase in the crystal grains, no single crystal tubes were produced. It was assumed that the operating temperature in these tests was not high enough to achieve single crystal growth. In FY 2012, a larger power supply was purchased and installed. With the new power supply, temperatures above the melting point of Nb were easily obtained regardless of the tube thickness. A series of crystallization tests was initiated to determine if indeed the operating temperature of the previous tests was too low to achieve single crystal growth. For these tests, the Nb tube OD remained at 3.8 cm and the wall thickness was 0.30 mm. The first test had an operating temperature of 2,000 ?C. and the operating temperature was increased by 50 ?C increments for each successive test. The final test was very near the Nb melting temperature, and indeed, the Nb tube eventually melted in the center of the tube. These tests showed that higher temperatures did yield larger grain sizes if the traverse rate was held constant at 5 cm per hour, but no single crystal tubes were produced even at the highest operating temperature. In addition, slowing the traverse rate to as low as 1 cm per hour did not yield a single crystal tube regardless of operating temperature. At this time, it

MURPHY, JAMES E [University of Nevada, Reno] [University of Nevada, Reno

2013-02-28T23:59:59.000Z

235

SHORT-TUBE SUBCRITICAL FLOW Enerag Division  

E-Print Network (OSTI)

#12;SHORT-TUBE SUBCRITICAL FLOW Y. C. Mei Enerag Division Oak Ridge National Laboratory Oak Ridge-tube subcritical flow. For short tubes used as refrigerant expansion devices, the orifice model is found inadequate-TUBE SUBCRITICAL FLOW INTRODUCTION Much theoretical and experimental work regarding short tube fluid flow has

Oak Ridge National Laboratory

236

2014 Tube -1 STANDING WAVES  

E-Print Network (OSTI)

2014 Tube - 1 STANDING WAVES IN AN AIR COLUMN The objective of the experiment is: · To study the harmonic structure of standing waves in an air column. APPARATUS: Computer, FFTScope software, PC speaker, meterstick, sound tube apparatus, thermometer, microphone INTRODUCTION traveling wave of sinusoidal shape

Glashausser, Charles

237

Helical tubes in crowded environments  

Science Journals Connector (OSTI)

When placed in a crowded environment, a semiflexible tube is forced to fold so as to make a more compact shape. One compact shape that often arises in nature is the tight helix, especially when the tube thickness is of comparable size to the tube length. In this paper we use an excluded volume effect to model the effects of crowding. This gives us a measure of compactness for configurations of the tube, which we use to look at structures of the semiflexible tube that minimize the excluded volume. We focus most of our attention on the helix and which helical geometries are most compact. We found helices of specific pitch to radius ratio 2.512 to be optimally compact. This is the same geometry that minimizes the global curvature of the curve defining the tube. We further investigate the effects of adding a bending energy or multiple tubes to begin to explore the more complete space of possible geometries a tube could form.

Yehuda Snir and Randall D. Kamien

2007-05-18T23:59:59.000Z

238

Assessment of strippable coatings for decontamination and decommissioning  

SciTech Connect

Strippable or temporary coatings were developed to assist in the decontamination of the Three Mile Island (TMI-2) reactor. These coatings have become a viable option during the decontamination and decommissioning (D and D) of both US Department of Energy (DOE) and commercial nuclear facilities to remove or fix loose contamination on both vertical and horizontal surfaces. A variety of strippable coatings are available to D and D professionals. However, these products exhibit a wide range of performance criteria and uses. The Hemispheric Center for Environmental Technology (HCET) at Florida International University (FIU) was commissioned to perform a 2-year investigation into strippable coatings. This investigation was divided into four parts: (1) identification of commercially available strippable coating products; (2) survey of D and D professionals to determine current uses of these coatings and performance criteria; (3) design and implementation of a non-radiological testing program to evaluate the physical properties of these coatings; and (4) design and implementation of a radiological testing program to determine decontamination factors and effects of exposure to ionizing radiation. Activities during fiscal year 1997 are described.

Ebadian, M.A.

1998-01-01T23:59:59.000Z

239

Tubing pressurized firing apparatus for a tubing conveyed perforating gun  

SciTech Connect

A tubing pressurized firing apparatus is shown for use with a tubing conveyed perforating gun of the type used to perforate a cased well bore. The firing apparatus has a tubular body with an upper end for connection in the well tubing string and with a lower end for connection to a well perforating gun. An inner mandrel is slidably mounted within the tubular body and has a ball seat formed in the interior bore thereof for receiving a ball dropped through the well tubing string. The ball and ball seat together form a pressure tight seal whereby tubing pressure in the well tubing string acts on the inner mandrel to slide the mandrel downwardly within the tubular body. A cocking mechanism located below the inner mandrel within the body includes a lockout member which is initially positioned between a detonating pin and a percussion detonator. The cocking mechanism is actuated by downward sliding movement of the inner mandrel to move the lockout member from between the detonating pin and percussion detonator whereby a subsequent release of tubing pressure and upward sliding movement of the inner mandrel exposes the detonating pin to the percussion detonator to actuate the detonator and fire the perforating gun.

Davies, D. L.

1985-11-26T23:59:59.000Z

240

Rosie - mobile robot worksystem for decommissioning and dismantling operations. Final report, April 1, 1996--January 31, 1997  

SciTech Connect

RedZone Robotics, Inc. has undertaken development of an advanced remote worksystem - Rosie - specifically designed to meet the challenges of performing a wide range of decontamination and dismantlement (D&D) operations in nuclear environments. The Rosie worksystem includes a locomotor, heavy manipulator, operator console, and control system for remote operations. The locomotor is a highly mobile platform with tether management and hydraulic power onboard. The heavy manipulator is a high-payload, long-reach boom used to deploy a wide variety of tools and/or sensors into the work area. Rosie`s advanced control system, broad work capabilities, and hardening/reliability for hazardous duty make it a new and unique capability that facilitates completion of significant cleanup projects throughout the Department of Energy (DOE) and private sector. Endurance testing of the first Rosie system from September 1995 to March 1996 has proven its capabilities and appropriateness for D&D applications. Design enhancements were incorporated into the second Rosie system to improve and add features necessary for deployment at a DOE facility decommissioning. This second Rosie unit was deployed to the Argonne National Laboratory`s CP-5 reactor facility in early December 1996, and it is currently being used in the decommissioning of the reactor there. This report will overview this second Rosie system and the design enhancements made to it based on the lessons learned during the design, fabrication, and testing of the first Rosie system. The Rosie system has been designed to be a versatile and adaptable tool that can be used in many different applications in D&D work at nuclear facilities. It can carry a wide variety of tooling, sensors, and other robotic equipment at the tip of its heavy manipulator, and it can deploy those items to many different hazardous work areas. Rosie`s capabilities and system design address the need for durability and reliability in these environments.

NONE

1998-12-31T23:59:59.000Z

Note: This page contains sample records for the topic "tube project decommissioning" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


241

Identification of sensitivity genes involved in teratogen-induced neural tube defects  

E-Print Network (OSTI)

that NTDs have a strong genetic component to their development. My project is designed to examine differential expression patterns of genes within the neural tube cells of inbred LM/Bc mouse fetuses following exposure to the known teratogenic agent...

Hayes, Blaine G

2013-02-22T23:59:59.000Z

242

Analysis of conjugate heat transfer in tube-in-block heat exchangers for some engineering applications.  

E-Print Network (OSTI)

??This project studied the effect of different parameters on the conjugate heat transfer in tube-in-block heat exchangers for various engineering applications. These included magnetic coolers… (more)

Gari, Abdullatif Abdulhadi

2006-01-01T23:59:59.000Z

243

E-Print Network 3.0 - accelerator drift-tube braze-joint Sample...  

NLE Websites -- All DOE Office Websites (Extended Search)

DRIFTTUBE LINAC FOR THE ISAC PROJECT AT TRIUMF Summary: , 105 MHz variable energy drift tube linac (DTL) to accelerate ions of 13 qA 16 to a final energy... A SEPARATED...

244

Combustion-thermoelectric tube  

SciTech Connect

In direct combustion-thermoelectric energy conversion, direct fuel injection and reciprocation of the air flowing in a solid matrix are combined with the solid conduction to allow for obtaining super-adiabatic temperatures at the hot junctions. While the solid conductivity is necessary, the relatively large thermal conductivity of the available high-temperature thermoelectric materials (e.g., Si-Ge alloys) results in a large conduction loss from the hot junctions and deteriorates the performance. Here a combustion-thermoelectric tube is introduced and analyzed. Radially averaged temperatures are used for the fluid and solid phases. A combination of external cooling of the cold junctions, and direct injection of the fuel, has been used to increase the energy conversion efficiency for low thermal conductivity, high-melting temperature thermoelectric materials. The parametric study (geometry, flow, stoichiometry, materials) shows that with the current high figure of merit, high temperature Si{sub 0.7}Ge{sub 0.3} properties, a conversion efficiency of about 11% is achievable. With lower thermal conductivities for these high-temperature materials, efficiencies about 25% appear possible. This places this energy conversion in line with the other high efficiency, direct electric power generation methods.

Park, C.W.; Kaviany, M.

1999-07-01T23:59:59.000Z

245

Method of making straight fuel cell tubes  

DOE Patents (OSTI)

A method and an apparatus for making straight fuel cell tubes are disclosed. Extruded tubes comprising powders of fuel cell material and a solvent are dried by rotating the extruded tubes. The rotation process provides uniform circumferential drying which results in uniform linear shrinkage of the tubes. The resultant dried tubes are very straight, thereby eliminating subsequent straightening steps required with conventional processes. The method is particularly useful for forming inner air electrode tubes of solid oxide fuel cells.

Borglum, Brian P. (Edgewood, PA)

2001-01-01T23:59:59.000Z

246

Decommissioning and PIE of the MEGAPIE spallation target  

SciTech Connect

A key experiment in the Accelerated Driven Systems roadmap, the MEGAwatt PIlot Experiment (MEGAPIE) (1 MW) was initiated in 1999 in order to design and build a liquid lead-bismuth spallation target, then to operate it into the Swiss spallation neutron facility SINQ at Paul Scherrer Institute. The target has been designed, manufactured, and tested during integral tests, before irradiation carried out end of 2006. During irradiation, neutron and thermo hydraulic measurements were performed allowing deep interpretation of the experiment and validation of the models used during design phase. The decommissioning, Post Irradiation Examinations and waste management phases were defined properly. The phases dedicated to cutting, sampling, cleaning, waste management, samples preparation and shipping to various laboratories were performed by PSI teams: all these phases constitute a huge work, which allows now to perform post-irradiation examination (PIE) of structural material, irradiated in relevant conditions. Preliminary results are presented in the paper, they concern chemical characterization. The following radio-nuclides have been identified by ?-spectrometry: {sup 60}Co, {sup 101}Rh, {sup 102}Rh, {sup 108m}Ag, {sup 110m}Ag, {sup 133}Ba, {sup 172}Hf/Lu, {sup 173}Lu, {sup 194}Hg/Au, {sup 195}Au, {sup 207}Bi. For some of these nuclides the activities can be easily evaluated from ?-spectrometry results ({sup 207}Bi, {sup 194}Hg/Au), while other nuclides can only be determined after chemical separations ({sup 108m}Ag, {sup 110m}Ag, {sup 195}Au, {sup 129}I, {sup 36}Cl and ?-emitting {sup 208-210}Po). The concentration of {sup 129}I is lower than expected. The chemical analysis already performed on spallation and corrosion products in the lead-bismuth eutectic (LBE) are very relevant for further applications of LBE as a spallation media and more generally as a coolant.

Latge, C.; Henry, J. [CEA-Cadarache, DEN-DTN, 13108 Saint-Paul-les-Durance (France); Wohlmuther, M.; Dai, Y.; Gavillet, D.; Hammer, B.; Heinitz, S.; Neuhausen, J.; Schumann, D.; Thomsen, K.; Tuerler, A.; Wagner, W. [PSI, Villigen (Switzerland); Gessi, A. [ENEA, Brasimone (Italy); Guertin, A. [CNRS, Subatech, Nantes (France); Konstantinovic, M. [SCK-CEN, Mol (Belgium); Lindau, R. [KIT, Karlsruhe (Germany); Maloy, S. [DOE-LANL, Los Alamos (United States); Saito, S. [JAEA, Tokai (Japan)

2013-07-01T23:59:59.000Z

247

Microhole Coiled Tubing Bottom Hole Assemblies  

SciTech Connect

The original objective of the project, to deliver an integrated 3 1/8-inch diameter Measurement While Drilling (MWD) and Logging While Drilling (LWD) system for drilling small boreholes using coiled tubing drilling, has been achieved. Two prototype systems have been assembled and tested in the lab. One of the systems has been successfully tested downhole in a conventional rotary drilling environment. Development of the 3 1/8-inch system has also lead to development and commercialization of a slightly larger 3.5-inch diameter system. We are presently filling customer orders for the 3.5-inch system while continuing with commercialization of the 3 1/8-inch system. The equipment developed by this project will be offered for sale to multiple service providers around the world, enabling the more rapid expansion of both coiled tubing drilling and conventional small diameter drilling. The project was based on the reuse of existing technology whenever possible in order to minimize development costs, time, and risks. The project was begun initially by Ultima Labs, at the time a small company ({approx}12 employees) which had successfully developed a number of products for larger oil well service companies. In September, 2006, approximately 20 months after inception of the project, Ultima Labs was acquired by Sondex plc, a worldwide manufacturer of downhole instrumentation for cased hole and drilling applications. The acquisition provided access to proven technology for mud pulse telemetry, downhole directional and natural gamma ray measurements, and surface data acquisition and processing, as well as a global sales and support network. The acquisition accelerated commercialization through existing Sondex customers. Customer demand resulted in changes to the product specification to support hotter (150 C) and deeper drilling (20,000 psi pressure) than originally proposed. The Sondex acquisition resulted in some project delays as the resistivity collar was interfaced to a different MWD system and also as the mechanical design was revised for the new pressure requirements. However, the Sondex acquisition has resulted in a more robust system, secure funding for completion of the project, and more rapid commercialization.

Don Macune

2008-06-30T23:59:59.000Z

248

Standard Guide for Environmental Monitoring Plans for Decommissioning of Nuclear Facilities  

E-Print Network (OSTI)

1.1 This guide covers the development or assessment of environmental monitoring plans for decommissioning nuclear facilities. This guide addresses: (1) development of an environmental baseline prior to commencement of decommissioning activities; (2) determination of release paths from site activities and their associated exposure pathways in the environment; and (3) selection of appropriate sampling locations and media to ensure that all exposure pathways in the environment are monitored appropriately. This guide also addresses the interfaces between the environmental monitoring plan and other planning documents for site decommissioning, such as radiation protection, site characterization, and waste management plans, and federal, state, and local environmental protection laws and guidance. This guide is applicable up to the point of completing D&D activities and the reuse of the facility or area for other purposes.

American Society for Testing and Materials. Philadelphia

2010-01-01T23:59:59.000Z

249

Tube-wave seismic imaging  

DOE Patents (OSTI)

The detailed analysis of cross well seismic data for a gas reservoir in Texas revealed two newly detected seismic wave effects, recorded approximately 2000 feet above the reservoir. A tube-wave (150) is initiated in a source well (110) by a source (111), travels in the source well (110), is coupled to a geological feature (140), propagates (151) through the geological feature (140), is coupled back to a tube-wave (152) at a receiver well (120), and is and received by receiver(s) (121) in either the same (110) or a different receiving well (120). The tube-wave has been shown to be extremely sensitive to changes in reservoir characteristics. Tube-waves appear to couple most effectively to reservoirs where the well casing is perforated, allowing direct fluid contact from the interior of a well case to the reservoir.

Korneev, Valeri A [LaFayette, CA

2009-05-05T23:59:59.000Z

250

Tube-wave seismic imaging  

DOE Patents (OSTI)

The detailed analysis of cross well seismic data for a gas reservoir in Texas revealed two newly detected seismic wave effects, recorded approximately 2000 feet above the reservoir. A tube-wave (150) is initiated in a source well (110) by a source (111), travels in the source well (110), is coupled to a geological feature (140), propagates (151) through the geological feature (140), is coupled back to a tube-wave (152) at a receiver well (120), and is and received by receiver(s) (121) in either the same (110) or a different receiving well (120). The tube-wave has been shown to be extremely sensitive to changes in reservoir characteristics. Tube-waves appear to couple most effectively to reservoirs where the well casing is perforated, allowing direct fluid contact from the interior of a well case to the reservoir.

Korneev, Valeri A. (Lafayette, CA); Bakulin, Andrey (Houston, TX)

2009-10-13T23:59:59.000Z

251

Low-level and transuranic waste transportation, disposal, and facility decommissioning cost sensitivity analysis  

SciTech Connect

The Systems Design Study (SDS) identified technologies available for the remediation of low-level and transuranic waste stored at the Radioactive Waste Management Complex`s Subsurface Disposal Area at the Idaho National Engineering Laboratory. The SDS study intentionally omitted the costs of transportation and disposal of the processed waste and the cost of decommissioning the processing facility. This report provides a follow-on analysis of the SDS to explore the basis for life-cycle cost segments of transportation, disposal, and facility decommissioning; to determine the sensitivity of the cost segments; and to quantify the life-cycle costs of the 10 ex situ concepts of the Systems Design Study.

Schlueter, R. [Bechtel National, Inc., San Francisco, CA (United States); Schafer, J.J. [EG and G Idaho, Inc., Idaho Falls, ID (United States)

1992-05-01T23:59:59.000Z

252

Low-level and transuranic waste transportation, disposal, and facility decommissioning cost sensitivity analysis  

SciTech Connect

The Systems Design Study (SDS) identified technologies available for the remediation of low-level and transuranic waste stored at the Radioactive Waste Management Complex's Subsurface Disposal Area at the Idaho National Engineering Laboratory. The SDS study intentionally omitted the costs of transportation and disposal of the processed waste and the cost of decommissioning the processing facility. This report provides a follow-on analysis of the SDS to explore the basis for life-cycle cost segments of transportation, disposal, and facility decommissioning; to determine the sensitivity of the cost segments; and to quantify the life-cycle costs of the 10 ex situ concepts of the Systems Design Study.

Schlueter, R. (Bechtel National, Inc., San Francisco, CA (United States)); Schafer, J.J. (EG and G Idaho, Inc., Idaho Falls, ID (United States))

1992-05-01T23:59:59.000Z

253

Criticality safety aspects of decontamination and decommissioning at defense nuclear facilities  

SciTech Connect

Defense nuclear facilities have operated for forty years with a well-defined mission to produce weapons components for the nation. With the end of the cold war, the facilities` missions have changed to one of decontamination and decommissioning. Off-normal operations and use of new procedures, such as will exist during these activities, have often been among the causal factors in previous criticality accidents at process facilities. This paper explores the similarities in causal factors in previous criticality accidents to the conditions existing in current defense nuclear facilities undergoing the transition to decontamination and decommissioning. Practices to reduce the risk to workers, the public, and the environment are recommended.

Croucher, D.W.

1994-02-01T23:59:59.000Z

254

Decommissioning an Active Historical Reactor Facility at the Savannah River Site - 13453  

SciTech Connect

The Savannah River Site (SRS) is an 802 square-kilometer United States Department of Energy (US DOE) nuclear facility located along the Savannah River near Aiken, South Carolina, where Management and Operations are performed by Savannah River Nuclear Solutions (SRNS). In 2004, DOE recognized SRS as structure within the Cold War Historic District of national, state and local significance composed of the first generation of facilities constructed and operated from 1950 through 1989 to produce plutonium and tritium for our nation's defense. DOE agreed to manage the SRS 105-C Reactor Facility as a potentially historic property due to its significance in supporting the U.S. Cold War Mission and for potential for future interpretation. This reactor has five primary areas within it, including a Disassembly Basin (DB) that received irradiated materials from the reactor, cooled them and prepared the components for loading and transport to a Separation Canyon for processing. The 6,317 square meter area was divided into numerous work/storage areas. The walls between the individual basin compartments have narrow vertical openings called 'slots' that permit the transfer of material from one section to another. Data indicated there was over 830 curies of radioactivity associated with the basin sediments and approximately 9.1 M liters of contaminated water, not including a large quantity of activated reactor equipment, scrap metal, and debris on the basin floor. The need for an action was identified in 2010 to reduce risks to personnel in the facility and to eliminate the possible release of contaminants into the environment. The release of DB water could potentially migrate to the aquifer and contaminate groundwater. DOE, its regulators [U. S. Environmental Protection Agency (USEPA)-Region 4 and the South Carolina Department of Health and Environmental Control (SCDHEC)] and the SC Historical Preservation Office (SHPO) agreed/concurred to perform a non-time critical removal action for the In Situ Decommissioning (ISD) of the 105-C Disassembly Basin. ISD consisted of stabilization/isolation of remaining contaminated water, sediment, activated reactor equipment, and scrap metal by filling the DB with underwater non-structural grout to the appropriate (-4.877 meter) grade-level, thence with dry area non-structural grout to the final -10 centimeter level. The roof over the DB was preserved due to its potential historical significance and to prevent the infiltration of precipitation. Forced evaporation was the form of treatment implemented to remove the approximately 9.1 M liters of contaminated basin water. Using specially formulated grouts, irradiated materials and sediment were treated by solidification/isolation thus reducing their mobility, reducing radiation exposure and creating an engineered barrier thereby preventing access to the contaminants. Grouting provided a low permeability barrier to minimize any potential transport of contaminants to the aquifer. Efforts were made to preserve the historical significance of the Reactor in accordance with the National Historic Preservation Act. ISD provides a cost effective means to isolate and contain residual radioactivity from past nuclear operations allowing natural radioactive decay to reduce hazards to manageable levels. This method limits release of radiological contamination to the environment, minimizes radiation exposure to workers, prevents human/animal access to the hazardous substances, and allows for ongoing monitoring of the decommissioned facility. Field construction was initiated in August 2011; evaporator operations commenced January 2012 and ended July 2012 with over 9 M liters of water treated/removed. Over 8,525 cubic meters of grout were placed, completing in August 2012. The project completed with an excellent safety record, on schedule and under budget. (authors)

Bergren, Christopher L.; Long, J. Tony; Blankenship, John K. [Savannah River Nuclear Solutions, LLC, Bldg. 730-4B, Aiken, SC 29808 (United States)] [Savannah River Nuclear Solutions, LLC, Bldg. 730-4B, Aiken, SC 29808 (United States); Adams, Karen M. [United States Department of Energy, Bldg. 730-B, Aiken, SC 29808 (United States)] [United States Department of Energy, Bldg. 730-B, Aiken, SC 29808 (United States)

2013-07-01T23:59:59.000Z

255

Uranium Neutron Coincidence Collar Model Utilizing Boron-10 Lined Tubes  

SciTech Connect

The Department of Energy Office of Nuclear Safeguards and Security (NA-241) is supporting the project Coincidence Counting With Boron-Based Alternative Neutron Detection Technology at Pacific Northwest National Laboratory (PNNL) for the development of a 3He proportional counter alternative neutron coincidence counter. The goal of this project is to design, build and demonstrate a system based upon 10B-lined proportional tubes in a configuration typical for 3He-based coincidence counter applications. This report, providing results for model development of Alternative Boron-Based Uranium Neutron Coincidence Collar (ABUNCL) designs, is a deliverable under Task 2 of the project.

Rogers, Jeremy L.; Ely, James H.; Kouzes, Richard T.; Lintereur, Azaree T.; Siciliano, Edward R.

2012-09-18T23:59:59.000Z

256

Interim Report: Coiled Tubing Drilling and Intervention System Using Cost Effective Vessel  

NLE Websites -- All DOE Office Websites (Extended Search)

DOCUMENT TITLE: DOCUMENT TITLE: Self Supporting Riser Technology to Enable Coiled Tubing Intervention for Deepwater Wells Document No.: 08121-1502-12 RPSEA PROJECT TITLE: Coil Tubing Drilling and Intervention System Using a Cost Effective Vessel RPSEA Project No.: 08121-1502 01 April 2011 Charles R. Yemington, PE Project Manager Nautilus International 400 North Sam Houston Parkway East, Suite 105 Houston, Texas 77060 RPSEA Project No.: 08121-1502 Coiled Tubing Drilling and Intervention System Using a Cost Effective Vessel RPSEA Project 08121-1502 01 April 2011 Page 2 of 91 LEGAL NOTICE This report was prepared by Nautilus International, LLC. as an account of work sponsored by the Research Partnership to Secure Energy for America (RPSEA). RPSEA members, the

257

Project 261  

NLE Websites -- All DOE Office Websites (Extended Search)

NOVEL CORROSION SENSOR FOR ADVANCED NOVEL CORROSION SENSOR FOR ADVANCED FOSSIL ENERGY POWER SYSTEMS Description The overall objective of this proposed project is to develop a new technology for on-line corrosion monitoring based on an innovative concept. The specific objectives and corresponding tasks are (1) develop the sensor and electronic measurement system; (2) evaluate and improve the system in a laboratory muffle furnace; and (3) evaluate and improve the system through tests conducted in a pilot-scale coal combustor (~1 MW). Fireside corrosion refers to the metal loss caused by chemical reactions on surfaces exposed to the combustion environment. Such corrosion is the leading mechanism for boiler tube failures and is a serious concern for current and future energy plants due to the introduction of technologies targeting emissions

258

DECOMMISSIONING CHALLENGES AT THE ROCKY FLATS ENVIRONMENTAL TECHNOLOGY SITE  

SciTech Connect

This paper presents a discussion of the demolition of the Building 788 cluster at the Rocky Flats Environmental Technology Site (RFETS) in Golden, Colorado. The Building 788 Cluster was a Resource Conservation and Recovery Act (RCRA) permitted storage facilities and ancillary structures. Topics covered include the methods employed for Project Planning, Regulatory Compliance, Waste Management, Hazard Identification, Radiological Controls, Risk Management, Field Implementation, and Cost Schedule control, and Lessons Learned and Project Closeout.

Dorr, K. A.; Hoover, J.

2002-02-25T23:59:59.000Z

259

Conceptual Decontamination and Decommissioning Plan for the Waste Isolation Pilot Plant  

SciTech Connect

The Conceptual Decontamination and Decommissioning Plan (D&D) was developed as a concept for progressing from the final actions of the Disposal Phase, through the Decontamination and Decommissioning Phase, and into the initiation of the Long-Term Monitoring Phase. This plan was written in a manner that coincides with many of the requirements specified in DOE Order 5820.2A. Radioactive Waste Management; ASTM El 167 87, Standard Guide for Radiation Protection Program for Decommissioning Operations; and other documents listed in Attachment 3 of the D&D Plan. However, this conceptual plan does not meet all of the requirements necessary for a Decontamination and Decommissioning plan necessary for submission to the U.S. Congress in accordance with the Land Withdrawal Act (P.L. 102-579). A complete D&D plan that will meet the requirements of all of these documents and of the Land Withdrawal Act will be prepared and submitted to Congress by October 1997.

Westinghouse Electric Corporation Waste Isolation Division, now Washington TRU Solutions LLC

1995-01-30T23:59:59.000Z

260

EIS-0364: Decommissioning of the Fast Flux Test Facility, Hanford Site, Richland, WA  

Energy.gov (U.S. Department of Energy (DOE))

The U.S. Department of Energy (DOE) announces its intent to prepare an Environmental Impact Statement (EIS), pursuant to the National Environmental Policy Act of 1969 (NEPA), on proposed decommissioning of the Fast Flux Test Facility (FFTF) at the Hanford Site, Richland, Washington.

Note: This page contains sample records for the topic "tube project decommissioning" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


261

An evaluation of the dismantling technologies for decommissioning of nuclear power plants  

Science Journals Connector (OSTI)

Abstract This paper is to suggest an evaluation method on the dismantling technologies for decommissioning of nuclear power plants. The parameters of evaluation are performance impacts, site-specific impacts, safety impacts, and cost impacts. The evaluation model was provided and applied for dismantling of a steam generator.

KwanSeong Jeong; ByungSeon Choi; Jeikwon Moon; Dongjun Hyun; JongHwan Lee; IkJune Kim; GeunHo Kim; JaeSeok Seo

2014-01-01T23:59:59.000Z

262

Allowable Residual Contamination Levels in soil for decommissioning the Shippingport Atomic Power Station site  

SciTech Connect

As part of decommissioning the Shippingport Atomic Power Station, a fundamental concern is the determination of Allowable Residual Contamination Levels (ARCL) for radionuclides in the soil at the site. The ARCL method described in this report is based on a scenario/exposure-pathway analysis and compliance with an annual dose limit for unrestricted use of the land after decommissioning. In addition to naturally occurring radionuclides and fallout from weapons testing, soil contamination could potentially come from five other sources. These include operation of the Shippingport Station as a pressurized water reactor, operations of the Shippingport Station as a light-water breeder, operation of the nearby Beaver Valley reactors, releases during decommissioning, and operation of other nearby industries, including the Bruce-Mansfield coal-fired power plants. ARCL values are presented for 29 individual radionculides and a worksheet is provided so that ARCL values can be determined for any mixture of the individual radionuclides for any annual dose limit selected. In addition, a worksheet is provided for calculating present time soil concentration value that will decay to the ARCL values after any selected period of time, such as would occur during a period of restricted access. The ARCL results are presented for both unconfined (surface) and confined (subsurface) soil contamination. The ARCL method and results described in this report provide a flexible means of determining unrestricted-use site release conditions after decommissioning the Shippingport Atomic Power Station.

Kennedy, W.E. Jr.; Napier, B.A.; Soldat, J.K.

1983-09-01T23:59:59.000Z

263

Erosion of heat exchanger tubes in fluidized beds. Annual report, 1990  

SciTech Connect

This final report describes the activities of the 3-year project entitled ``Erosion of Heat Exchanger Tubes In Fluidized Beds.`` which was completed at the end of 1990. Project accomplishments include the collection of a substantial body of wear data In a 24in. {times} 24in. fluidized bed, comparative wear results In a 6in. {times} 6in. fluidized bed, the development of a dragometer and the collection of a comprehensive set of drag force data in the 24in. {times} 24in. bed, Fast Fourier Transform (FFT) analysis of bubble probe data to establish dominant bubble frequencies in the 24in. {times} 24in. bed, the use of a heat flux gauge for measurement of heat transfer coefficients in the 24in. {times} 24in. bed and the modeling of the tube wear in the 24in. {times} 24in. bed. Analysis of the wear data from the 24in. square bed indicates that tube wear increases with increase in superficial velocity, and with increase in tube height. The latter effect is a result of the tubes higher up in the bed seeing greater movement of dense phase than tubes lower down In the bed. In addition, tube wear was found to decrease with increase in particle size, for constant superficial velocity. Three models of tube wear were formulated and provided acceptable prediction of wear when compared with the experimental data.

Johnson, E.K.; Flemmer, R.L.C.

1991-01-01T23:59:59.000Z

264

Core-tube data logger  

SciTech Connect

Wireline core drilling, increasingly used for geothermal exploration, employs a core-tube to capture a rock core sample during drilling. Three types of core-tube data loggers (CTDL) have been built and tested to date by Sandia national Laboratories. They are: (1) temperature-only logger, (2) temperature/inclinometer logger and (3) heat-shielded temperature/inclinometer logger. All were tested during core drilling operations using standard wireline diamond core drilling equipment. While these tools are designed for core-tube deployment, the tool lends itself to be adapted to other drilling modes and equipment. Topics covered in this paper include: (1) description on how the CTDLs are implemented, (2) the components of the system, (3) the type of data one can expect from this type of tool, (4) lessons learned, (5) comparison to its counterpart and (6) future work.

Henfling, J.A.; Normann, R.A.; Knudsen, S.; Drumheller, D.

1997-01-01T23:59:59.000Z

265

Flash photolysis-shock tube studies  

SciTech Connect

Even though this project in the past has concentrated on the measurement of thermal bimolecular reactions of atomic species with stable molecules by the flash or laser photolysis-shock tube (FP- or LP-ST) method using atomic resonance absorption spectrometry (ARAS) as the diagnostic technique, during the past year the authors have concentrated on studies of the thermal decompositions of selected chlorocarbon molecules. These studies are necessary if the degradation of chlorine containing organic molecules by incineration are to be understood at the molecular level. Clearly, destruction of these molecules will not only involve abstraction reactions, when possible, but also thermal decomposition followed by secondary reactions of the initially formed atoms and radicals. Studies on the thermal decomposition of CH{sub 3}Cl are complete, and the curve-of-growth for Cl-atom atomic resonance absorption has been determined. The new thermal decomposition studies are similar to those already reported for CH{sub 3}Cl.

Michael, J.V. [Argonne National Laboratory, IL (United States)

1993-12-01T23:59:59.000Z

266

Project Year Project Title  

E-Print Network (OSTI)

the cost of the project to labor only. The efficacy of the examples will be assessed through their useProject Year 2012-2013 Project Title Sight-Reading at the Piano Project Team Ken Johansen, Peabody) Faculty Statement The goal of this project is to create a bank of practice exercises that student pianists

Gray, Jeffrey J.

267

Project Year Project Team  

E-Print Network (OSTI)

design goals for this project include low cost (less than $30 per paddle) and robustness. The projectProject Year 2001 Project Team Faculty: Allison Okamura, Mechanical Engineering, Whiting School Project Title Haptic Display of Dynamic Systems Audience 30 to 40 students per year, enrolled

Gray, Jeffrey J.

268

Project Year Project Team  

E-Print Network (OSTI)

-year section of the summer project will cost $1344.) This project will be measured by the CER surveys conductedProject Year 2005 Project Team Sean Greenberg, Faculty, Philosophy Department, Krieger School of Arts & Sciences; Kevin Clark, Student, Philosophy Department, Krieger School of Arts & Sciences Project

Gray, Jeffrey J.

269

Recommended values for the distribution coefficient (Kd) to be used in dose assessments for decommissioning the Zion Nuclear Power Plant  

SciTech Connect

ZionSolutions is in the process of decommissioning the Zion Nuclear Power Plant. The site contains two reactor Containment Buildings, a Fuel Building, an Auxiliary Building, and a Turbine Building that may be contaminated. The current decommissioning plan involves removing all above grade structures to a depth of 3 feet below grade. The remaining underground structures will be backfilled. The remaining underground structures will contain low amounts of residual licensed radioactive material. An important component of the decommissioning process is the demonstration that any remaining activity will not cause a hypothetical individual to receive a dose in excess of 25 mrem/y as specified in 10CFR20 SubpartE.

Sullivan T.

2014-06-09T23:59:59.000Z

270

Continuation of Studies on Development of ODS Heat Exchanger Tubing  

SciTech Connect

The Department of Energy (DOE), National Energy Technology Center (NETL), has initiated a strategic plan for the development of advanced technologies needed to design and build fossil fuel plants with very high efficiency and environmental performance. These plants, referred to as 'Vision 21' and FutureGen programs by DOE, will produce electricity, chemicals, fuels, or a combination of these products, and possibly secondary products such as steam/heat for industrial use. MA956 is a prime candidate material being considered for a high temperature heat exchanger in the 'Vision 21' and FutureGen programs. This material is an oxide dispersion strengthened (ODS) alloy; however, there are some gaps in the data required to commit to the use of these alloys in a full-size plant. To fill the technology gaps for commercial production and use of the material for 'Advanced Power Generation Systems' this project has performed development activity to significant increase in circumferential strength of MA956 as compared to currently available material, investigated bonding technologies for bonding tube-to-tube joints through joining development, and performed tensile, creep and fire-side corrosion tests to validate the use and fabrication processes of MA956 to heat exchanger tubing applications. Development activities within this projected has demonstrated increased circumferential strength of MA956 tubes through flow form processing. Of the six fabrication technologies for bonding tube-to-tube joints, inertia friction welding (IFW) and flash butt welding (FBW) were identified as processes for joining MA956 tubes. Tensile, creep, and fire-side corrosion test data were generated for both base metal and weld joints. The data can be used for design of future systems employing MA956. Based upon the positive development activities, two test probes were designed and fabricated for field exposure testing at 1204 C ({approx}2200 F) flue gas. The probes contained tube portions with FBW and IFW welded MA956. Field testing of the probes and remaining heat exchanger design activity will be performed by Oak Ridge National Laboratory under DOE Contract DE-AC05-00OR22725.

Lawrence Brown; David Workman; Bimal Kad; Gaylord Smith; Archie Robertson; Ian Wright

2008-04-15T23:59:59.000Z

271

Project Year Project Team  

E-Print Network (OSTI)

Project Year 2002 Project Team Faculty: Louise Pasternack, Chemistry Department, Krieger School, Krieger School of Arts & Sciences Project Title Introductory Chemistry Lab Demonstrations Audience an interactive virtual lab manual that will facilitate understanding of the procedures and techniques required

Gray, Jeffrey J.

272

Action Memorandum for the Engineering Test Reactor under the Idaho Cleanup Project  

SciTech Connect

This Action Memorandum documents the selected alternative for decommissioning of the Engineering Test Reactor at the Idaho National Laboratory under the Idaho Cleanup Project. Since the missions of the Engineering Test Reactor Complex have been completed, an engineering evaluation/cost analysis that evaluated alternatives to accomplish the decommissioning of the Engineering Test Reactor Complex was prepared adn released for public comment. The scope of this Action Memorandum is to encompass the final end state of the Complex and disposal of the Engineering Test Reactor vessol. The selected removal action includes removing and disposing of the vessel at the Idaho CERCLA Disposal Facility and demolishing the reactor building to ground surface.

A. B. Culp

2007-01-26T23:59:59.000Z

273

Project Year Project Team  

E-Print Network (OSTI)

(Karl) Zhang, Undergraduate Student, Biomedical Engineering, Whiting School of Engineering; Cheryl Kim Audio, Digital Video Project Abstract The goal of this project is to develop online modular units

Gray, Jeffrey J.

274

Apparatus for connecting aligned abutted tubes  

DOE Patents (OSTI)

An apparatus for connecting abutted tubes and for maintaining their rotary alignment during connection. The apparatus comprises first and second tubes, a rotation prevention element, a collar and a retainer. Each tube has inside and outside walls, and first and second ends, each end having an inside and outside edge. The first tube has portions defining a first plurality of cavities located at the outside edge of its first end. An external threaded portion is on the outside wall of the first tube and next to the first plurality of cavities. The second tube has portions defining a second plurality of cavities located at the outside edge of its first end. The first plurality has a different number than the second plurality. The first ends of the first and second tubes have substantially the same outside diameter and are abutted during connection so that an orifice is formed whenever first and second tube cavities substantially overlap. A rotation prevension element is placed in the orifice to prevent rotation of the first and second tubes. A collar with an internal threaded portion is slidably disposed about the second tube. The internal threaded portion engages the external threaded portion of the first tube to connect the tubes. A lip connected to the collar prevents separation of the collar from the second tube.

Williams, R.E.

1984-11-29T23:59:59.000Z

275

Line Projects  

NLE Websites -- All DOE Office Websites (Extended Search)

(PDCI) Upgrade Project Whistling Ridge Energy Project Line Rebuild, Relocation and Substation Projects Wind Projects Line Projects BPA identifies critical infrastructure and...

276

Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 13: Part 2, Indexes. Environmental Restoration Program  

SciTech Connect

This is part 2 of a bibliography on nuclear facility decommissioning and site remedial action. This report contains indexes on the following: authors, corporate affiliation, title words, publication description, geographic location, subject category, and key word.

Goins, L.F.; Webb, J.R.; Cravens, C.D.; Mallory, P.K.

1992-09-01T23:59:59.000Z

277

Performance of drift tubes under high radiation  

E-Print Network (OSTI)

In this thesis, the aging and the rejuvenation of an ATLAS proportional drift tube are described. Firstly, the Diethorn model of gain is tested using pressure and sense-wire voltage measurements. The drift tube was then ...

Shi, Yue, S.B. Massachusetts Institute of Technology

2005-01-01T23:59:59.000Z

278

Fracture compliance estimation using borehole tube waves  

E-Print Network (OSTI)

We tested two models, one for tube-wave generation and the other for tube-wave attenuation at a fracture intersecting a borehole that can be used to estimate fracture compliance, fracture aperture, and lateral extent. In ...

Bakku, Sudhish Kumar

279

Two phase flow in capillary tubes  

E-Print Network (OSTI)

The flow of two phases, gas and liquid, has been studied in horizontal tubes of capillary diameter. The flow has been primarily studied in the regime where the gas flows as long bubbles separated from the wall of the tube ...

Suo, Mikio

1963-01-01T23:59:59.000Z

280

Project Year Project Title  

E-Print Network (OSTI)

that incorporate video taped procedures for student preview. Solution This project will create videos for more to study the procedure and techniques before coming to class. Our previous fellowship project addressedProject Year 2009 Project Title Enhancing Biology Laboratory Preparation through Video

Gray, Jeffrey J.

Note: This page contains sample records for the topic "tube project decommissioning" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


281

Project Year Project Team  

E-Print Network (OSTI)

, there is no resource available to view the procedure before class. Solution The purpose of this project is to capture available to view the procedure before class. The purpose #12;of this project is to capture variousProject Year 2007 Project Team Kristina Obom, Faculty, Advanced Academic Programs, Krieger School

Gray, Jeffrey J.

282

Project Year Project Title  

E-Print Network (OSTI)

Project Year 2013-2014 Project Title German Online Placement Exam Project Team Deborah Mifflin to increased cost. As well, it lacked listening comprehension, writing and speaking components providing support, we will use Blackboard for this project. The creation will require numerous steps

Gray, Jeffrey J.

283

Project Definition Rating Index (PDRI) | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Project Definition Rating Index (PDRI) Project Definition Rating Index (PDRI) Project Definition Rating Index (PDRI) The Office of Environmental Management (EM) Project Definition Rating Index (EM-PDRI) is a modification of a commercially developed planning tool that has been tested by an EM team specifically for EM's projects. EM-PDRI Team members represent a number of EM sites, and have already used this project planning tool successfully. The EM-PDRI examines a wide range of project factors related to cost, scope, and schedule, and develops a numerical score as a measure of how well these factors are defined. It applies to all of EM's projects including Traditional/Construction; Environmental Remediation; and Facility Disposition (including Transition, Deactivation, and Decommissioning). If you have questions about the EM-PDRI, please

284

Stability of tube rows in crossflow. [LMFBR  

SciTech Connect

A mathematical model for the instability of tube rows subjected to crossflow is examined. The theoretical model, based on the fluid-force data for a pitch-to-diameter ratio of 1.33, provides additional insight into the instability phenomenon. Tests are also conducted for three sets of tube rows. The effects of mass ratio, tube pitch, damping, detuning and finned tubes are investigated. Theoretical results and experimental data are in good agreement.

Chen, S.S.; Jendrzejczyk, J.A.

1982-10-01T23:59:59.000Z

285

Environmental Assessment for Decontamination and Decommissioning of the Juggernaut Reactor at Argonne National Laboratory Â… East Argonne, Illinois  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

DOE/EA-1483 DOE/EA-1483 Environmental Assessment for Decontamination and Decommissioning of the Juggernaut Reactor at Argonne National Laboratory - East Argonne, Illinois March 2004 U.S. Department of Energy Chicago Operations Office Argonne Area Office Argonne, Illinois Environmental Assessment for Decontamination and Decommissioning of the Juggernaut Reactor at Argonne National Laboratory - East Argonne, Illinois Table of Contents Acronyms....................................................................................................................................... iii 1.0 Background ..........................................................................................................................1 1.1 Facility History ........................................................................................................1

286

Physical and Numerical Analysis of Extrusion Process for Production of Bimetallic Tubes  

SciTech Connect

Bimetallic tubes are used for very specific applications where one of the two metals provides strength and the other provides specific properties such as aqueous corrosion and carburization, coking resistance, and special electrical and thermal properties. Bimetallic tubes have application in pulp and paper industry for heat-recovery boilers, in the chemical industry for ethylene production, and in the petrochemical industry for deep oil well explorations. Although bimetallic tubes have major applications in energy-intensive industry, they often are not used because of their cost and manufacturing sources in the United States. This project was intended to address both of these issues.

Misiolek, W.Z.; Sikka, V.K.

2006-08-10T23:59:59.000Z

287

Spring/dimple instrument tube restraint  

DOE Patents (OSTI)

A nuclear fuel assembly for a pressurized water nuclear reactor has a spring and dimple structure formed in a non-radioactive insert tube placed in the top of a sensor receiving instrumentation tube thimble disposed in the fuel assembly and attached at a top nozzle, a bottom nozzle, and intermediate grids. The instrumentation tube thimble is open at the top, where the sensor or its connection extends through the cooling water for coupling to a sensor signal processor. The spring and dimple insert tube is mounted within the instrumentation tube thimble and extends downwardly adjacent the top. The springs and dimples restrain the sensor and its connections against lateral displacement causing impact with the instrumentation tube thimble due to the strong axial flow of cooling water. The instrumentation tube has a stainless steel outer sleeve and a zirconium alloy inner sleeve below the insert tube adjacent the top. The insert tube is relatively non-radioactivated inconel alloy. The opposed springs and dimples are formed on diametrically opposite inner walls of the insert tube, the springs being formed as spaced axial cuts in the insert tube, with a web of the insert tube between the cuts bowed radially inwardly for forming the spring, and the dimples being formed as radially inward protrusions opposed to the springs. 7 figures.

DeMario, E.E.; Lawson, C.N.

1993-11-23T23:59:59.000Z

288

Ionization tube simmer current circuit  

DOE Patents (OSTI)

A highly efficient flash lamp simmer current circuit utilizes a fifty percent duty cycle square wave pulse generator to pass a current over a current limiting inductor to a full wave rectifier. The DC output of the rectifier is then passed over a voltage smoothing capacitor through a reverse current blocking diode to a flash lamp tube to sustain ionization in the tube between discharges via a small simmer current. An alternate embodiment of the circuit combines the pulse generator and inductor in the form of an FET off line square wave generator with an impedance limited step up output transformer which is then applied to the full wave rectifier as before to yield a similar simmer current.

Steinkraus, Jr., Robert F. (Livermore, CA)

1994-01-01T23:59:59.000Z

289

Ionization tube simmer current circuit  

DOE Patents (OSTI)

A highly efficient flash lamp simmer current circuit utilizes a fifty percent duty cycle square wave pulse generator to pass a current over a current limiting inductor to a full wave rectifier. The DC output of the rectifier is then passed over a voltage smoothing capacitor through a reverse current blocking diode to a flash lamp tube to sustain ionization in the tube between discharges via a small simmer current. An alternate embodiment of the circuit combines the pulse generator and inductor in the form of an FET off line square wave generator with an impedance limited step up output transformer which is then applied to the full wave rectifier as before to yield a similar simmer current. 6 figures.

Steinkraus, R.F. Jr.

1994-12-13T23:59:59.000Z

290

Overview of the DOE studies of recovery boiler floor tube cracking  

SciTech Connect

Cracking of the stainless steel layer of coextruded 304L/SA210 recovery boiler floor tubes has been observed in an increasing number of black liquor recovery boilers. Because failure of such tubes is a serious safety concern as well as an economic issue, this project was initiated with the objective of identifying alternate materials or process changes that would prevent tube cracking. Tensile stresses are essential for the most likely failure mechanisms, i.e., fatigue or stress corrosion cracking, therefore stresses were measured at room temperature and modeling was used to predict stresses under operating conditions. Laboratory studies have identified conditions under which composite tubes crack due to thermal fatigue and stress corrosion. Floor tube temperature measurements have defined the magnitude and frequency of temperature fluctuations experienced by such tubes, and smelt corrosion studies have measured the degradation rate when molten smelt comes in contact with tubes. Based on these observations, certain materials appear more likely to resist cracking and certain process changes should help avoid conditions that cause composite tube cracking.

Keiser, J.R.; Taljat, B.; Wang, X.L. [and others

1998-03-01T23:59:59.000Z

291

Uranium Enrichment Decontamination and Decommissioning Fund's Fiscal Year 2011 Financial Statement Audit  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Uranium Uranium Enrichment Decontamination and Decommissioning Fund's Fiscal Year 2011 Financial Statement Audit OAS-FS-13-02 October 2012 September 7, 2012 Mr. Gregory Friedman Inspector General U.S. Department of Energy 1000 Independence Avenue, S.W. Room 5D-039 Washington, DC 20585 Dear Mr. Friedman: We have audited the financial statements of the Department of Energy's (the Department) Uranium Enrichment Decontamination and Decommissioning Fund (D&D Fund) as of and for the year ended September 30, 2011, and have issued our report thereon dated September 7, 2012. In planning and performing our audit of the consolidated financial statements, in accordance with auditing standards generally accepted in the United States of America, we considered the Department's internal control

292

Environmental Assessment for decommissioning the Strategic Petroleum Reserve Weeks Island Facility, Iberia Parish, Louisiana  

SciTech Connect

The Strategic Petroleum Reserve (SPR) Weeks Island site is one of five underground salt dome crude oils storage facilities operated by the Department of Energy (DOE). It is located in Iberia Parish, Louisiana. The purpose of the proposed action is to decommission the Weeks Island crude oil storage after the oil inventory has been transferred to other SPR facilities. Water intrusion into the salt dome storage chambers and the development of two sinkholes located near the aboveground facilities has created uncertain geophysical conditions. This Environmental Assessment describes the proposed decommissioning operation, its alternatives, and potential environmental impacts. Based on this analyses, DOE has determined that the proposed action is not a major Federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act (NEPA) and has issued the Finding of No Significant Impact (FONSI).

NONE

1995-12-01T23:59:59.000Z

293

Cost update technology, safety, and costs of decommissioning a reference uranium hexafluoride conversion plant  

SciTech Connect

The purpose of this study is to update the cost estimates developed in a previous report, NUREG/CR-1757 (Elder 1980) for decommissioning a reference uranium hexafluoride conversion plant from the original mid-1981 dollars to values representative of January 1993. The cost updates were performed by using escalation factors derived from cost index trends over the past 11.5 years. Contemporary price quotes wee used for costs that have increased drastically or for which is is difficult to find a cost trend. No changes were made in the decommissioning procedures or cost element requirements assumed in NUREG/CR-1757. This report includes only information that was changed from NUREG/CR-1757. Thus, for those interested in detailed descriptions and associated information for the reference uranium hexafluoride conversion plant, a copy of NUREG/CR-1757 will be needed.

Miles, T.L.; Liu, Y.

1995-08-01T23:59:59.000Z

294

Cold cathode vacuum discharge tube  

DOE Patents (OSTI)

A cold cathode vacuum discharge tube, and method for making same, with an interior surface of the trigger probe coated with carbon deposited by carbon vapor deposition (CVD) or diamond-like carbon (DLC) deposition. Preferably a solid graphite insert is employed in the probe-cathode structure in place of an aluminum bushing employed in the prior art. The CVD or DLC probe face is laser scribed to allow resistance trimming to match available trigger voltage signals and to reduce electrical aging.

Boettcher, Gordon E. (Albuquerque, NM)

1998-01-01T23:59:59.000Z

295

Turbine nozzle stage having thermocouple guide tube  

DOE Patents (OSTI)

A guide tube is fixed adjacent opposite ends in outer and inner covers of a nozzle stage segment. The guide tube is serpentine in shape between the outer and inner covers and extends through a nozzle vane. An insert is disposed in the nozzle vane and has apertures to accommodate serpentine portions of the guide tube. Cooling steam is also supplied through chambers of the insert on opposite sides of a central insert chamber containing the guide tube. The opposite ends of the guide tube are fixed to sleeves, in turn fixed to the outer and inner covers.

Schotsch, Margaret Jones (Greer, SC); Kirkpatrick, Francis Lawrence (late of Galway, NY); Lapine, Eric Michael (Northwood, NH)

2002-01-01T23:59:59.000Z

296

Decontamination and decommissioning surveillance and maintenance report for FY 1991. Environmental Restoration Program  

SciTech Connect

The Decontamination and Decommissioning (D&D) Program has three distinct phases: (1) surveillance and maintenance (S&M); (2) decontamination and removal of hazardous materials and equipment (which DOE Headquarters in Washington, D.C., calls Phase I of remediation); and (3) decommissioning and ultimate disposal, regulatory compliance monitoring, and property transfer (which DOE Headquarters calls Phase II of remediation). A large part of D&D is devoted to S&M at each of the sites. Our S&M activities, which are performed on facilities awaiting decommissioning, are designed to minimize potential hazards to human health and the environment by: ensuring adequate containment of residual radioactive and hazardous materials; and, providing physical safety and security controls to minimize potential hazards to on-site personnel and the general public. Typically, we classify maintenance activities as either routine or special (major repairs). Routine maintenance includes such activities as painting, cleaning, vegetation control, minor structural repairs, filter changes, and building system(s) checks. Special maintenance includes Occupational Safety and Health Act facility upgrades, roof repairs, and equipment overhaul. Surveillance activities include inspections, radiological measurements, reporting, records maintenance, and security (as required) for controlling and monitoring access to facilities. This report summarizes out FY 1991 S&M activities for the Tennessee plant sites, which include the K-25 Site, the Gas Centrifuge facilities, ORNL, and the Y-12 Plant.

Not Available

1991-12-01T23:59:59.000Z

297

ENVIRONMENTAL PROBLEMS ASSOCIATED WITH DECOMMISSIONING THE CHERNOBYL NUCLEAR POWER PLANT COOLING POND  

SciTech Connect

Decommissioning of nuclear power plants and other nuclear fuel cycle facilities has been an imperative issue lately. There exist significant experience and generally accepted recommendations on remediation of lands with residual radioactive contamination; however, there are hardly any such recommendations on remediation of cooling ponds that, in most cases, are fairly large water reservoirs. The literature only describes remediation of minor reservoirs containing radioactive silt (a complete closure followed by preservation) or small water reservoirs resulting in reestablishing natural water flows. Problems associated with remediation of river reservoirs resulting in flooding of vast agricultural areas also have been described. In addition, the severity of environmental and economic problems related to the remedial activities is shown to exceed any potential benefits of these activities. One of the large, highly contaminated water reservoirs that require either remediation or closure is Karachay Lake near the MAYAK Production Association in the Chelyabinsk Region of Russia where liquid radioactive waste had been deep well injected for a long period of time. Backfilling of Karachay Lake is currently in progress. It should be noted that secondary environmental problems associated with its closure are considered to be of less importance since sustaining Karachay Lake would have presented a much higher radiological risk. Another well-known highly contaminated water reservoir is the Chernobyl Nuclear Power Plant (ChNPP) Cooling Pond, decommissioning of which is planned for the near future. This study summarizes the environmental problems associated with the ChNPP Cooling Pond decommissioning.

Farfan, E.

2009-09-30T23:59:59.000Z

298

Environmental Problems Associated With Decommissioning The Chernobyl Nuclear Power Plant Cooling Pond  

SciTech Connect

Decommissioning of nuclear power plants and other nuclear fuel cycle facilities has been an imperative issue lately. There exist significant experience and generally accepted recommendations on remediation of lands with residual radioactive contamination; however, there are hardly any such recommendations on remediation of cooling ponds that, in most cases, are fairly large water reservoirs. The literature only describes remediation of minor reservoirs containing radioactive silt (a complete closure followed by preservation) or small water reservoirs resulting in reestablishing natural water flows. Problems associated with remediation of river reservoirs resulting in flooding of vast agricultural areas also have been described. In addition, the severity of environmental and economic problems related to the remedial activities is shown to exceed any potential benefits of these activities. One of the large, highly contaminated water reservoirs that require either remediation or closure is Karachay Lake near the MAYAK Production Association in the Chelyabinsk Region of Russia where liquid radioactive waste had been deep well injected for a long period of time. Backfilling of Karachay Lake is currently in progress. It should be noted that secondary environmental problems associated with its closure are considered to be of less importance since sustaining Karachay Lake would have presented a much higher radiological risk. Another well-known highly contaminated water reservoir is the Chernobyl Nuclear Power Plant (ChNPP) Cooling Pond, decommissioning of which is planned for the near future. This study summarizes the environmental problems associated with the ChNPP Cooling Pond decommissioning.

Farfan, E. B.; Jannik, G. T.; Marra, J. C.; Oskolkov, B. Ya.; Bondarkov, M. D.; Gaschak, S. P.; Maksymenko, A. M.; Maksymenko, V. M.; Martynenko, V. I.

2009-11-09T23:59:59.000Z

299

Technology, safety and costs of decommissioning a reference boiling water reactor power station. Volume 1. Main report. Technical report, September 1977-October 1979  

SciTech Connect

Technology, safety and cost information is given for the conceptual decommissioning of a large (1100MWe) boiling water reactor (BWR) power station. Three approaches to decommissioning, immediate dismantlement, safe storage with deferred dismantlement and entombment, were studied to obtain comparisons between costs, occupational radiation doses, potential dose to the public and other safety impacts. It also shows the sensitivity of decommissioning safety and costs to the power rating of a BWR in the range of 200 to 1100 MWE.

Oak, H.D.; Holter, G.M.; Kennedy, W.E. Jr.; Konzek, G.J.

1980-06-01T23:59:59.000Z

300

Projectivities and Projective Embeddings  

Science Journals Connector (OSTI)

In this chapter, we aim to prove some of the main achievements in the theory of generalized polygons. First, we want to show what the little projective group and the groups of projectivities of some Moufang po...

Hendrik van Maldeghem

1998-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "tube project decommissioning" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


301

Project Overview  

NLE Websites -- All DOE Office Websites (Extended Search)

Questions Keeler-Pennwalt Wood Pole Removal Line Projects Line Rebuild, Relocation and Substation Projects Spacer Damper Replacement Program Wind Projects Project Overview BPA...

302

Project Year Project Title  

E-Print Network (OSTI)

operators, matrix indexing, vector computations, loops, functions, and plotting graphs, among others basic arithmetic operators, matrix indexing, and vector computations in MATLAB. After creatingProject Year 2011-2012 Project Title Online Tutorial for MATLAB Project Team Eileen Haase, Whiting

Gray, Jeffrey J.

303

Project Year Project Team  

E-Print Network (OSTI)

Project Year 2005 Project Team Krysia Hudson, Faculty, School of Nursing, Undergraduate Instruction for Educational Resources Project Title Enhanced Web-based Learning Environments for Beginning Nursing Students (e.g., demonstrations of procedures or tasks) into the WBL systems, it will be possible to increase

Gray, Jeffrey J.

304

Project Year Project Team  

E-Print Network (OSTI)

Project Year 2002 Project Team Faculty: Michael McCloskey, Cognitive Science/Neuroscience, Krieger of Arts & Sciences Project Title Cognitive Neuropsychology Audience The initial audience to access. The current procedure calls for individual students or researchers to contact the faculty member

Gray, Jeffrey J.

305

Project Year Project Title  

E-Print Network (OSTI)

Project Year 2011-2012 Project Title Using M-Health and GIS Technology in the Field to Improve into teams and having each team use a different m-health data collection tool (e.g., cellular phones, smart health patterns. The Tech Fellow, Jacqueline Ferguson, will assist in creating an m-health project

Gray, Jeffrey J.

306

Project Year Project Team  

E-Print Network (OSTI)

Project Year 2002 Project Team Faculty: Gregory Hager, Computer Science, Whiting School of Engineering Fellow: Alan Chen, Biomedical Engineering, Whiting School of Engineering Project Title Robotics is complicated, time-consuming, and costly, making a robot for an introductory-level class is not practical

Gray, Jeffrey J.

307

Project Proposal Project Logistics  

E-Print Network (OSTI)

Project Proposal · Project Logistics: ­ 2-3 person teams ­ Significant implementation, worth 55 and anticipated cost of copying to/from host memory. IV. Intellectual Challenges - Generally, what makes this computation worthy of a project? - Point to any difficulties you anticipate at present in achieving high

Hall, Mary W.

308

PROJECT MANGEMENT PLAN EXAMPLES Prepare Project Support Plans and  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Environmental Plan Examples Environmental Plan Examples Example 51 8.1 ENVIRONMENTAL STRATEGY A significant part of the strategy for maintaining compliance with environmental regulatory requirements during the PFP Stabilization and Deactivation Project is to apply the process described in the Tri-Party Agreement, Section 8.0, "Facility Decommissioning Process." The Section 8.0 process will allow the DOE to develop agreements with the State and Federal regulatory agencies facilitating timely stabilization of the PFP inventory of plutonium-bearing materials, deactivation of the PFP Complex, and perhaps elimination of all above ground hazards at the PFP Complex through dismantlement of the buildings and structures. The Section 8.0 process also provides the means for DOE to ensure the public and stakeholders get an opportunity

309

Ultrasonic Concentration in a Line-Driven Cylindrical Tube  

SciTech Connect

The fractionation of particles from their suspending fluid or noninvasive micromanipulation of particles in suspension has many applications ranging from the recovery of valuable reagents from process flows to the fabrication of microelectromechanical devices. Techniques based on size, density, solubility, or electromagnetic properties exist for fulfilling these needs, but many particles have traits that preclude their use such as small size, neutral buoyancy, or uniform electromagnetic characteristics. While separation by those techniques may not be possible, often compressibility differences exist between the particle and fluid that would allow fractionation by acoustic forces. The potential of acoustic separation is known, but due to inherent difficulties in achieving and maintaining accurate alignment of the transduction system, it is rarely utilized. The objective of this project is to investigate the use of structural excitation as a potentially efficient concentration/fractionation method for particles in suspension. It is demonstrated that structural excitation of a cylindrically symmetric cavity, such as a tube, allows non-invasive, fast, and low power concentration of particles suspended in a fluid. The inherent symmetry of the system eliminates the need for careful alignment inherent in current acoustic concentration devices. Structural excitation distributes the acoustic field throughout the volume of the cavity, which also significantly reduces temperature gradients and acoustic streaming in the fluid; cavitation is no longer an issue. The lowest-order coupled modes of a long cylindrical glass tube and fluid-filled cavity, driven by a line contact, are tuned, via material properties and aspect ratio, to achieve a coupled dipolar vibration of the system, shown to generate efficient concentration of particles to the central axis of the tube. A two dimensional elastodynamic model of the system was developed and subsequently utilized to optimize particle concentration within the system. The effects of tubing, fluid, and particle material properties, tube geometry, fluid flow, and tube length on the structural excitation and consequently power requirements and concentration quality within the tube were investigated theoretically and experimentally. Limitations of the method are discussed, as well as ways to minimize or compensate for deleterious effects. Finally a preliminary demonstration of the efficacy of acoustic concentration is presented.

G.R. Goddard

2004-12-15T23:59:59.000Z

310

Industry Related Projects [Laser Applications Laboratory] - Nuclear  

NLE Websites -- All DOE Office Websites (Extended Search)

Industry Related Projects Industry Related Projects Capabilities Engineering Experimentation Reactor Safety Experimentation Aerosol Experiments System Components Laser Applications Overview Laser Oil & Gas Well Drilling Laser Heat Treatment Laser Welding of Metals On-line Monitoring Laser Beam Delivery Laser Glazing of Railroad Rails High Power Laser Beam Delivery Decontamination and Decommissioning Refractory Alloy Welding Robots Applications Other Facilities Other Capabilities Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE on Flickr Laser Applications Laboratory Industry related projects Bookmark and Share LASER OIL & GAS WELL DRILLING Using high-power lasers to drill and complete gas & oil wells LASER HEAT TREATMENT Optimization of laser beam heat treatment (Caterpillar and USCAR)

311

Large Diameter Lasing Tube Cooling Arrangement  

DOE Patents (OSTI)

A cooling structure (16) for use inside a ceramic cylindrical tube (11) of a metal vapor laser (10) to cool the plasma in the tube (11), the cooling structure (16) comprising a plurality of circular metal members (17,31) and mounting members (18, 34) that position the metal members (17,31) coaxially in the tube (11) to form an annular lasing volume, with the metal members (17, 31) being axially spaced from each other along the length of the tube (11) to prevent the metal members from shorting out the current flow through the plasma in the tube (11) and to provide spaces through which the heat from localized hot spots in the plasma may radiate to the other side of the tube (11).

Hall, Jerome P.; Alger, Terry W.; Anderson, Andrew T.; Arnold, Philip A.

2004-05-18T23:59:59.000Z

312

Tube support grid and spacer therefor  

DOE Patents (OSTI)

A tube support grid and spacers therefor provide radially inward preloading of heat exchange tubes to minimize stress upon base welds due to differential thermal expansion. The grid comprises a concentric series of rings and spacers with opposing concave sides for conforming to the tubes and V-shaped ends to provide resilient flexibility. The flexibility aids in assembly and in transmitting seismic vibrations from the tubes to a shroud. The tube support grid may be assembled in place to achieve the desired inwardly radial preloading of the heat exchange tubes. Tab and slot assembly further minimizes stresses in the system. The radii of the grid rings may be preselected to effect the desired radially inward preloading.

Ringsmuth, Richard J. (Solano Beach, CA); Kaufman, Jay S. (Del Mar, CA)

1986-01-01T23:59:59.000Z

313

A Built for Purpose Micro-Hole Coiled Tubing Rig (MCTR)  

SciTech Connect

This report will serve as the final report on the work performed from the contract period October 2005 thru April 2007. The project 'A Built for Purpose Microhole Coiled Tubing Rig (MCTR)' purpose was to upgrade an existing state-of-the-art Coiled Tubing Drilling Rig to a Microhole Coiled Tubing Rig (MCTR) capable of meeting the specifications and tasks of the Department of Energy. The individual tasks outlined to meet the Department of Energy's specifications are: (1) Concept and development of lubricator and tool deployment system; (2) Concept and development of process control and data acquisition; (3) Concept and development of safety and efficiency improvements; and (4) Final unit integration and testing. The end result of the MCTR upgrade has produced a unit capable of meeting the following requirements: (1) Capable of handling 1-inch through 2-3/8-inch coiled tubing (Currently dressed for 2-3/8-inch coiled tubing and capable of running up to 3-1/2-inch coiled tubing); (2) Capable of drilling and casing surface, intermediate, production and liner hole intervals; (3) Capable of drilling with coiled tubing and has all controls and installation piping for a top drive; (4) Rig is capable of running 7-5/8-inch range 2 casing; and (5) Capable of drilling 5,000 ft true vertical depth (TVD) and 6,000 ft true measured depth (TMD).

Bart Patton

2007-09-30T23:59:59.000Z

314

Pilot-scale treatability testing -- Recycle, reuse, and disposal of materials from decontamination and decommissioning activities: Soda blasting demonstration  

SciTech Connect

The US Department of Energy (DOE) is in the process of defining the nature and magnitude of decontamination and decommissioning (D and D) obligations at its sites. With disposal costs rising and available storage facilities decreasing, DOE is exploring and implementing new waste minimizing D and D techniques. Technology demonstrations are being conducted by LMES at a DOE gaseous diffusion processing plant, the K-25 Site, in Oak Ridge, Tennessee. The gaseous diffusion process employed at Oak Ridge separated uranium-235 from uranium ore for use in atomic weapons and commercial reactors. These activities contaminated concrete and other surfaces within the plant with uranium, technetium, and other constituents. The objective of current K-25 D and D research is to make available cost-effective and energy-efficient techniques to advance remediation and waste management methods at the K-25 Site and other DOE sites. To support this objective, O`Brien and Gere tested a decontamination system on K-25 Site concrete and steel surfaces contaminated with radioactive and hazardous waste. A scouring system has been developed that removes fixed hazardous and radioactive surface contamination and minimizes residual waste. This system utilizes an abrasive sodium bicarbonate medium that is projected at contaminated surfaces. It mechanically removes surface contamination while leaving the surface intact. Blasting residuals are captured and dissolved in water and treated using physical/chemical processes. Pilot-scale testing of this soda blasting system and bench and pilot-scale treatment of the generated residuals were conducted from December 1993 to September 1994.

NONE

1995-08-01T23:59:59.000Z

315

Sampling artifacts from conductive silicone tubing  

NLE Websites -- All DOE Office Websites (Extended Search)

Sampling artifacts from conductive silicone tubing Sampling artifacts from conductive silicone tubing Title Sampling artifacts from conductive silicone tubing Publication Type Journal Article Year of Publication 2009 Authors Timko, Michael T., Zhenhong Yu, Jesse Kroll, John T. Jayne, Douglas R. Worsnop, Richard C. Miake-Lye, Timothy B. Onasch, David Liscinsky, Thomas W. Kirchstetter, Hugo Destaillats, Amara L. Holder, Jared D. Smith, and Kevin R. Wilson Journal Aerosol Science and Technology Volume 43 Issue 9 Pagination 855-865 Date Published 06/03/2009 Abstract We report evidence that carbon impregnated conductive silicone tubing used in aerosol sampling systems can introduce two types of experimental artifacts: (1) silicon tubing dynamically absorbs carbon dioxide gas, requiring greater than 5 minutes to reach equilibrium and (2) silicone tubing emits organic contaminants containing siloxane that are adsorbed onto particles traveling through it and onto downstream quartz fiber filters. The consequence can be substantial for engine exhaust measurements as both artifacts directly impact calculations of particulate mass-based emission indices. The emission of contaminants from the silicone tubing can result in overestimation of organic particle mass concentrations based on real-time aerosol mass spectrometry and the off-line thermal analysis of quartz filters. The adsorption of siloxane contaminants can affect the surface properties of aerosol particles; we observed a marked reduction in the water-affinity of soot particles passed through conductive silicone tubing. These combined observations suggest that the silicone tubing artifacts may have wide consequence for the aerosol community and the tubing should, therefore, be used with caution. Contamination associated with the use of silicone tubing was observed at ambient temperature and, in some cases, was enhanced by mild heating (<70°C) or pre-exposure to a solvent (methanol). Further evaluation is warranted to quantify systematically how the contamination responds to variations in system temperature, physicochemical particle properties, exposure to solvent, sample contact time, tubing age, and sample flow rates.

316

Major Risk Factors to the Integrated Facility Disposition Project  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Oak Ridge Reservation Tennessee Major Risk Factors to the Integrated Facility Disposition Project (IFDP) Challenge The scope of the Integrated Facility Disposition Project (IFDP) needs to comprehensively address a wide range of environmental management risks at the Oak Ridge Reservation (ORO). These include: environmental remediation, regulatory compliance, deactivation and decommissioning (D&D) activities, and disposition of legacy materials and waste, along with the ongoing modernization, reindustrialization, and reconfiguration initiatives at the Oak Ridge National Laboratory and at the Y-12 National Security Complex. The balancing of the broad nature of these activities and issues at ORO are a key challenge for the IFDP especially since their interrelationship is not always obvious.

317

Allowable residual-contamination levels for decommissioning facilities in the 100 areas of the Hanford Site  

SciTech Connect

This report contains the results of a study sponsored by UNC Nuclear Industries to determine Allowable Residual Contamination Levels (ARCL) for five generic categories of facilities in the 100 Areas of the Hanford Site. The purpose of this study is to provide ARCL data useful to UNC engineers in conducting safety and cost comparisons for decommissioning alternatives. The ARCL results are based on a scenario/exposure-pathway analysis and compliance with an annual dose limit for three specific modes of future use of the land and facilities. These modes of use are restricted, controlled, and unrestricted. The information on ARCL values for restricted and controlled use provided by this report is intended to permit a full consideration of decommissioning alternatives. ARCL results are presented both for surface contamination remaining in facilities (in dpm/100 cm/sup 2/), and for unconfined surface and confined subsurface soil conditions (in pCi/g). Two confined soil conditions are considered: contamination at depths between 1 and 4 m, and contamination at depths greater than or equal to 5 m. A set of worksheets are presented in an appendix for modifying the ARCL values to accommodate changes in the radionuclide mixture or concentrations, to consider the impacts of radioactive decay, and to predict instrument responses. Finally, a comparison is made between the unrestricted release ARCL values for the 100 Area facilities and existing decommissioning and land disposal regulations. For surface contamination, the comparison shows good agreement. For soil contamination, the comparison shows good agreement if reasonable modification factors are applied to account for the differences in modeling soil contamination and licensed low-level waste.

Kennedy, W.E. Jr.; Napier, B.A.

1983-07-01T23:59:59.000Z

318

Office of Environmental Management Uranium Enrichment Decontamination and Decommissioning Fund financial statements, September 30, 1995 and 1994  

SciTech Connect

The Energy Policy Act of 1992 (Act) requires the Department of Energy to retain ownership and responsibility for the costs of environmental cleanup resulting from the Government`s operation of the three gaseous diffusion facilities located at the K-25 site in Oak Ridge, Tennessee; Paducah, Kentucky; and Portsmouth, Ohio. The Act transferred the uranium enrichment enterprise to the United States Enrichment Corporation (USEC) as of July 1, 1993, and established the Uranium Enrichment Decontamination and Decommissioning Fund (D&D Fund) to: Pay for the costs of decontamination and decommissioning at the diffusion facilities; pay the annual costs for remedial action at the diffusion facilities to the extent that the amount in the Fund is sufficient; and reimburse uranium/thorium licensees for the costs of decontamination, decommissioning, reclamation, and other remedial actions which are incident to sales to the Government.

NONE

1996-02-21T23:59:59.000Z

319

Environmental Assessment for Decontamination and Decommissioning of the Juggernaut Reactor at Argonne National Laboratory Â… East Argonne, Illinois  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Finding of No Significant Impact Finding of No Significant Impact Proposed Decontamination and Decommissioning of the Juggernaut Reactor at Argonne National Laboratory - East Argonne, Illinois AGENCY: U. S. Department of Energy (DOE) ACTION: Finding of No Significant Impact (FONSI) SUMMARY: DOE has prepared an Environmental Assessment (EA), DOE/EA-1483, evaluating the decontamination and decommissioning of the Juggernaut Reactor at Argonne National Laboratory-East (ANL-E), in Argonne, Illinois. The decontamination and decommissioning of the reactor is needed to ensure the protection of the health and safety of the public, DOE and contractor employees, and the environment, consistent with DOE Order 5400.5, Radiation Protection of the Public and the Environment. Based on the analysis in the EA, DOE has determined that the proposed action does not

320

Leakage-flow-induced vibration of a tube-in-tube slip joint. [LMFBR  

SciTech Connect

The susceptibility of a cantilevered tube conveying water to self-excitation by leakage flow through a slip joint is assessed experimentally. The slip joint is formed by inserting a smaller, rigid tube into the free end of the cantilevered tube. Variations of the slip joint annular gaps and engagement lengths are tested, and several mechanisms for self-excitation are described.

Mulcahy, T.M.

1983-06-01T23:59:59.000Z

Note: This page contains sample records for the topic "tube project decommissioning" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


321

NETL: Deepwater Technology Projects  

NLE Websites -- All DOE Office Websites (Extended Search)

Deepwater Technology Deepwater Technology Deepwater Technology Offshore Architecture | Safety & Environmental | Other UDW Technology | Completed DW Projects Project Number Project Name Primary Performer 10121-4306-01 All Electric Subsea Autonomous High Integrity Pressure Protection System (HIPPS) Architecture GE Global Research 10121-4401-02 Ultra-Deepwater Riser Concepts for High Motion Vessels Stress Engineering Services, Inc. 10121-4405-02 Ultra-deepwater Dry Tree System for Drilling and Production in the Gulf of Mexico Det Norske Veritas 10121-4505-01 Coil Tubing Drilling and Intervention System Using Cost Effective Vessel Nautilus International, LLC 09121-3500-01 Intelligent Production System for Ultra-Deepwater with Short Hop Wireless Power and Wireless Data Transfer for Lateral Production Control and Optimization

322

REVIEW OF INDUSTRIES AND GOVERNMENT AGENCIES FOR TECHNOLOGIES APPLICABLE TO DEACTIVATION AND DECOMMISSIONING OF NUCLEAR WEAPONS FACILITIES  

SciTech Connect

The Deactivation and Decommissioning Focus Area's (DDFA's) mission is to develop, demonstrate, and deploy improved deactivation and decommissioning (D&D) technologies. This mission requires that emphasis be continually placed on identifying technologies currently employed or under development in other nuclear as well as nonnuclear industries and government agencies. In support of DDFA efforts to clean up the U.S. Department of Energy's (DOE's) radiologically contaminated surplus facilities using technologies that improve worker safety, reduce costs, and accelerate cleanup schedules, a study was conducted to identify innovative technologies developed for use in nonnuclear arenas that are appropriate for D&D applications.

Reilkoff, T. E.; Hetland, M. D.; O'Leary, E. M.

2002-02-25T23:59:59.000Z

323

Characterization of stainless steel 304 tubing  

SciTech Connect

Earlier studies have shown that stainless steel 304 (SS304) containing martensite is susceptible to hydrogen embrittlement. This generated concern regarding the structural integrity of SS304 tubing we use in the W87 pit tube. During surveillance operations, the pit tube undergoes a series of bending and straightening as it goes through a number of surveillance cycles. This motivated the study to characterize austenitic SS304 tubing obtained from Rocky Flats. The tubes continued to display structural soundness even after numerous repeated bending and straightening cycles. The minimum and maximum number of bends to failure occurred after 13 and 16 cycles, respectively. After 5 bends, both the inner and outer surfaces of the tubing showed no microcracks. When the bent tubing samples were pressurized and tested using deuterium at 74{degrees}C and at {approximately}78{degrees}C, they failed away from the bent area. Thus deuterium embrittlement of the bent SS304 tubing should not be a problem. Moreover, to increase our 95% confidence level to 5 bends, we are planning to perform at least four additional bends to failure tests.

Sunwoo, A.J.; Brooks, M.A.; Kervin, J.E.

1995-10-16T23:59:59.000Z

324

Sampling Artifacts from Conductive Silicone Tubing  

SciTech Connect

We report evidence that carbon impregnated conductive silicone tubing used in aerosol sampling systems can introduce two types of experimental artifacts: 1) silicon tubing dynamically absorbs carbon dioxide gas, requiring greater than 5 minutes to reach equilibrium and 2) silicone tubing emits organic contaminants containing siloxane that adsorb onto particles traveling through it and onto downstream quartz fiber filters. The consequence can be substantial for engine exhaust measurements as both artifacts directly impact calculations of particulate mass-based emission indices. The emission of contaminants from the silicone tubing can result in overestimation of organic particle mass concentrations based on real-time aerosol mass spectrometry and the off-line thermal analysis of quartz filters. The adsorption of siloxane contaminants can affect the surface properties of aerosol particles; we observed a marked reduction in the water-affinity of soot particles passed through conductive silicone tubing. These combined observations suggest that the silicone tubing artifacts may have wide consequence for the aerosol community and should, therefore, be used with caution. Gentle heating, physical and chemical properties of the particle carriers, exposure to solvents, and tubing age may influence siloxane uptake. The amount of contamination is expected to increase as the tubing surface area increases and as the particle surface area increases. The effect is observed at ambient temperature and enhanced by mild heating (<100 oC). Further evaluation is warranted.

Timko, Michael T.; Yu, Zhenhong; Kroll, Jesse; Jayne, John T.; Worsnop, Douglas R.; Miake-Lye, Richard C.; Onasch, Timothy B.; Liscinsky, David; Kirchstetter, Thomas W.; Destaillats, Hugo; Holder, Amara L.; Smith, Jared D.; Wilson, Kevin R.

2009-05-15T23:59:59.000Z

325

Characterization of decontamination and decommissioning wastes expected from the major processing facilities in the 200 Areas  

SciTech Connect

This study was intended to characterize and estimate the amounts of equipment and other materials that are candidates for removal and subsequent processing in a solid waste facility when the major processing and handling facilities in the 200 Areas of the Hanford Site are decontaminated and decommissioned. The facilities in this study were selected based on processing history and on the magnitude of the estimated decommissioning cost cited in the Surplus Facilities Program Plan; Fiscal Year 1993 (Winship and Hughes 1992). The facilities chosen for this study include B Plant (221-B), T Plant (221-T), U Plant (221-U), the Uranium Trioxide (UO{sub 3}) Plant (224-U and 224-UA), the Reduction Oxidation (REDOX) or S Plant (202-S), the Plutonium Concentration Facility for B Plant (224-B), and the Concentration Facility for the Plutonium Finishing Plant (PFP) and REDOX (233-S). This information is required to support planning activities for current and future solid waste treatment, storage, and disposal operations and facilities.

Amato, L.C.; Franklin, J.D.; Hyre, R.A.; Lowy, R.M.; Millar, J.S.; Pottmeyer, J.A. [Los Alamos Technical Associates, Kennewick, WA (United States); Duncan, D.R. [Westinghouse Hanford Co., Richland, WA (United States)

1994-08-01T23:59:59.000Z

326

Independent Activity Report, West Valley Demonstration Project - July 2012  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

West Valley Demonstration Project - West Valley Demonstration Project - July 2012 Independent Activity Report, West Valley Demonstration Project - July 2012 July 2012 Operational Awareness Oversight of the West Valley Demonstration Project [HIAR WVDP-2012-07-30] The purpose of this Office of Health, Safety and Security (HSS) activity was for the HS-45 Site Lead to meet with Department of Energy (DOE) site personnel, tour the facilities, and obtain a status report on the upcoming activities at the West Valley Demonstration Project (WVDP). In the fall of 2011, a new contractor, CH2M Hill-B&W West Valley (CHBWV), was selected to perform site operations for Phase 1 decommissioning and facility disposition, including the Main Plant Process Building, the Low-Level Waste Treatment Facility, and other facilities.

327

Project Year Project Team  

E-Print Network (OSTI)

; Ian Sims, Student, Electrical and Computer Engineering, Whiting School of Engineering Project Title and Jazz Theory/Keyboard I & II. Technologies Used Digital Audio, Digital Video, Graphic Design, HTML

Gray, Jeffrey J.

328

NETL: Oil & Natural Gas Projects  

NLE Websites -- All DOE Office Websites (Extended Search)

Mud System for Microhole Coiled Tubing Drilling Mud System for Microhole Coiled Tubing Drilling DE-FC26-03NT15476 Project Goal The goal of the project is to develop an innovative mud system for coiled tubing drilling (CTD) and small-diameter holes (microholes) for vertical, horizontal and multilateral drilling and completion applications. The system will be able to mix the required fluids (water, oil, chemicals, muds, slurries), circulate that mixture downhole (modified 350 gpm @1,000 psi and 15 gpm@ 5,000 psi), clean and store (200 bbls) the base fluids, and be able to perform these functions in an underbalanced condition with zero discharge and low environmental impact. Another primary and most important goal of this project is to develop key components for a new abrasive slurry drilling system.

329

Summer Student Project Report  

E-Print Network (OSTI)

My project covered a preliminary R&D phase in which an HPD tube with 163-pixels and external readout was tested. The external readout electronics were based on the existing Beetle front-end chip. The HPD performance for single-photon detection was assessed. The experimental setup made use of a fast laser light sources and an electronics readout chain specifically developed for laboratory tests. In parallel to the measurements, I improved the software which was used to make measurements and to display the data in a useful way.

Kazan, Oguz

2013-01-01T23:59:59.000Z

330

The STACEE Project  

E-Print Network (OSTI)

The Solar Tower Atmospheric Cherenkov Effect Experiment (STACEE) is a telescope designed to explore the gamma-ray sky between 20 and 250 GeV using the atmospheric Cherenkov technique. STACEE is currently under construction. When completed, it will use 48 large heliostat mirrors at the solar research facility at Sandia National Laboratories (Albuquerque, NM) to reflect Cherenkov light created in gamma-ray air showers to secondary mirrors on a central tower. The secondary mirrors image this light onto photomultiplier tube cameras. This paper provides an overview of the STACEE project, including a description of the experimental site and an outline of the current design for the detector components.

Ong, R A; Ong, Rene A.; Covault, Corbin E.

1997-01-01T23:59:59.000Z

331

The STACEE Project  

E-Print Network (OSTI)

The Solar Tower Atmospheric Cherenkov Effect Experiment (STACEE) is a telescope designed to explore the gamma-ray sky between 20 and 250 GeV using the atmospheric Cherenkov technique. STACEE is currently under construction. When completed, it will use 48 large heliostat mirrors at the solar research facility at Sandia National Laboratories (Albuquerque, NM) to reflect Cherenkov light created in gamma-ray air showers to secondary mirrors on a central tower. The secondary mirrors image this light onto photomultiplier tube cameras. This paper provides an overview of the STACEE project, including a description of the experimental site and an outline of the current design for the detector components.

Rene A. Ong; Corbin E. Covault

1997-11-25T23:59:59.000Z

332

EERE PROJECT MANAGEMENT CENTER NEPA DETERMINATION RECIPIENT  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

!, !, u.s. DEPARThIENT OFENI'RGY EERE PROJECT MANAGEMENT CENTER NEPA DETERMINATION RECIPIENT :Advanced Magnet Lab, Inc. STATE : FL PROJECf TITLE: A Lightweight, Direct Drive, Fully Superconducting Generator for large Wind Turbines Page 1 of3 Funding Opportunity Announcement Number Procurement Instrument Number NEPA Control Number CID Number DE-FOA-0000439 DE-EEOOOS140 GFO-OOOS140-003 G05140 Based on my review of the information concerning tbe proposed action, as NEPA Compliance Officer (authorized under OOE Order 451.1A), I have made the following determination : ex. EA, EIS APPENDIX AND NUMBER: Description: 83.6 Small-scale research and de ve lopment, labo ratory o perations, and pilot projects Siting. construction, modification, operation. and decommiSSioning of facilities for smaliscale research

333

Multi-tube fuel nozzle with mixing features  

DOE Patents (OSTI)

A system includes a multi-tube fuel nozzle having an inlet plate and a plurality of tubes adjacent the inlet plate. The inlet plate includes a plurality of apertures, and each aperture includes an inlet feature. Each tube of the plurality of tubes is coupled to an aperture of the plurality of apertures. The multi-tube fuel nozzle includes a differential configuration of inlet features among the plurality of tubes.

Hughes, Michael John

2014-04-22T23:59:59.000Z

334

Detonation limits in rough walled tubes  

Science Journals Connector (OSTI)

Abstract The present paper reports the results of a study of detonation limits in rough tubes. Detonation velocity is measured by photodiodes and ionization probes spaced at 10 cm intervals along the length of the tube. Short lengths of smoked foils inserted into the core of the rough tube is used to register the structure of the detonation wave. Pressure transducers are also used to obtain the pressure profile. The results indicate that in rough tubes, the detonation velocity is generally much lower than the corresponding values for smooth tubes. The velocity decreases slowly at first and then more rapidly as the limit is approached. The velocity variation is generally continuous and at the limits, the failure velocity is of the order of about 0.4 V CJ for all cases. The detonation limits in rough tubes are found to be wider than for a smooth tube. This indicates that the turbulence generated by the wall roughness facilitates the propagation of the detonation and extends the limits. Smoked foil records show that in the core of the rough tube the detonation front has a cellular structure corresponding to the usual cellular structure due to instability of the detonation. Thus the intrinsic unstable cellular structure is quite robust and retains its global characteristics in spite of the large perturbations generated by the rough wall. The detonation in the core of the rough tube goes from multi-headed to single headed as the limit is approached. Past the single headed spin, the low velocity detonation has no cellular structure but consists of interacting weak transverse waves from the rough wall. The averaged pressure of the low velocity detonation front corresponds to about the constant volume explosion pressure, in accord with the velocity of the low velocity detonation.

Amanda Starr; John H.S. Lee; Hoi Dick Ng

2014-01-01T23:59:59.000Z

335

Revised analyses of decommissioning for the reference boiling water reactor power station. Effects of current regulatory and other considerations on the financial assurance requirements of the decommissioning rule and on estimates of occupational radiation exposure - appendices. Final report  

SciTech Connect

The NRC staff is in need of decommissioning bases documentation that will assist them in assessing the adequacy of the licensee submittals, from the viewpoint of both the planned actions, including occupational radiation exposure, and the probable costs. The purpose of this reevaluation study is to update the needed bases documentation. This report presents the results of a review and reevaluation of the PNL 1980 decommissioning study of the Washington Public Power Supply System`s Washington Nuclear Plant Two (WNP-2) located at Richland, Washington, including all identifiable factors and cost assumptions which contribute significantly to the total cost of decommissioning the plant for the DECON, SAFSTOR, and ENTOMB decommissioning alternatives. These alternatives now include an initial 5-7 year period during which time the spent fuel is stored in the spent fuel pool prior to beginning major disassembly or extended safe storage of the plant. Included for information (but not presently part of the license termination cost) is an estimate of the cost to demolish the decontaminated and clear structures on the site and to restore the site to a {open_quotes}green field{close_quotes} condition. This report also includes consideration of the NRC requirement that decontamination and decommissioning activities leading to termination of the nuclear license be completed within 60 years of final reactor shutdown, consideration of packaging and disposal requirements for materials whose radionuclide concentrations exceed the limits for Class C low-level waste (i.e., Greater-Than-Class C), and reflects 1993 costs for labor, materials, transport, and disposal activities. Sensitivity of the total license termination cost to the disposal costs at different low-level radioactive waste disposal sites, to different depths of contaminated concrete surface removal within the facilities, and to different transport distances is also examined.

Smith, R.I.; Bierschbach, M.C.; Konzek, G.J.; McDuffie, P.N.

1996-07-01T23:59:59.000Z

336

Recent Sodium Technology Development for the Decommissioning of the Rapsodie and Superphenix Reactors and the Management of Sodium Wastes  

SciTech Connect

The Commissariat a l'Energie Atomique (CEA) has recently developed and/or conducted experiments on several processes in support of the decommissioning of two French liquid-metal fast reactors (LMFRs), Rapsodie and Superphenix, as well as on the treatment of CEA sodium wastes. CEA has demonstrated that it is possible to define appropriate and efficient processes to meet the different situations encountered in decommissioning LMFRs. Mechanical techniques derived from standard technologies have been successfully applied to fast reactor decommissioning to complete primary vessel draining from sodium. In addition, specific chemical processes have been developed to deal safely with metallic sodium reactivity. Sodium-contaminated equipment has been successfully cleaned by reacting sodium with water mist in an atmosphere with carbon dioxide to form inert sodium carbonate. Bulk sodium has been successfully converted into aqueous caustic soda by injection of liquid-metallic sodium into sodium hydroxide solution. Several processes were also defined to deal with specific sodium wastes. In all cases the principle is based on a sodium/water chemical reaction where the released hydrogen and heat are controlled. With the development of a wide variety of processes, all steps in the decommissioning of LMFRs are assumed to be now properly mastered.

Rodriguez, G.; Gastaldi, O.; Baque, F. [Commissariat a l'Energie Atomique Cadarache (France)

2005-04-15T23:59:59.000Z

337

Decision to reorganise or reorganising decisions? A First-Hand Account of the Decommissioning of the Phnix Nuclear Power Plant  

E-Print Network (OSTI)

of the Decommissioning of the Phénix Nuclear Power Plant Melchior Pelleterat de Borde, MINES ParisTech, Christophe Martin looks at the effect of ongoing organisational changes taking place in a nuclear power plant being campaigns, the Phénix nuclear power plant was taken out of service at the end of 2009. The plant has two

Paris-Sud XI, Université de

338

Alternative Electrostatic Green's Function for a Long Tube. ...  

NLE Websites -- All DOE Office Websites (Extended Search)

Alternative Electrostatic Green's Function for a Long Tube. Alternative Electrostatic Green's Function for a Long Tube. Abstract: This note describes an expression for the...

339

Starter for inductively coupled plasma tube  

DOE Patents (OSTI)

A starter assembly is provided for use with an inductively coupled plasma (ICP) tube to reliably initiate a plasma at internal pressures above about 30 microns. A conductive probe is inserted within the inductor coil about the tube and insulated from the tube shield assembly. A capacitive circuit is arranged for momentarily connecting a high voltage radio-frequency generator to the probe while simultaneously energizing the coil. When the plasma is initiated the probe is disconnected from the generator and electrically connected to the shield assembly for operation. 1 fig.

Hull, D.E.; Bieniewski, T.M.

1988-08-23T23:59:59.000Z

340

Project Fact Sheet Project Brief  

E-Print Network (OSTI)

Project Fact Sheet Project Brief: Construction Project Team: Project Facts & Figures: Budget: £1.1M Funding Source: Departmental Construction Project Programme: Start on Site: November 2010 End Date : March 2011 Occupation Date: March 2011 For further information contact Project Manager as listed above

Note: This page contains sample records for the topic "tube project decommissioning" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


341

Project Fact Sheet Project Update  

E-Print Network (OSTI)

Project Fact Sheet Project Update: Project Brief: The works cover the refurbishment of floors 4, 5 operating theatre. The Bionanotechnology Centre is one of the projects funded from the UK Government's £20.imperial.ac.uk/biomedeng Construction Project Team: Project Facts & Figures: Budget: £13,095,963 Funding Source: SRIF II and Capital

342

Project Fact Sheet Project Brief  

E-Print Network (OSTI)

Project Fact Sheet Project Brief: This project refurbished half of the 5th and 7th floors on the Faculty of Medicine, please visit: http://www1.imperial.ac.uk/medicine/ Construction Project Team: Project Facts & Figures: Budget: £3,500,000 Funding Source: SRIF III Construction Project Programme: Start

343

Expectations on Documented Safety Analysis for Deactivated Inactive Nuclear Facilities in a State of Long Term Surveillance & Maintenance or Decommissioning  

SciTech Connect

DOE promulgated 10 CFR 830 ''Nuclear Safety Management'' on October 10, 2000. Section 204 of the Rule requires that contractors at DOE hazard category 1, 2, and 3 nuclear facilities develop a ''Documented Safety Analysis'' (DSA) that summarizes the work to be performed, the associated hazards, and hazard controls necessary to protect workers, the public, and the environment. Table 2 of Appendix A to the rule has been provided to ensure that DSAs are prepared in accordance with one of the available predetermined ''safe harbor'' approaches. The table presents various acceptable safe harbor DSAs for different nuclear facility operations ranging from nuclear reactors to decommissioning activities. The safe harbor permitted for decommissioning of a nuclear facility encompasses methods described in DOE-STD-1 120-98, ''Integration of Environment, Safety and Health into Facility Disposition Activities,'' and provisions in 29 CFR 1910.120 or 29 CFR 1926.65 (HAZWOPER). Additionally, an evaluation of public safety impacts and development of necessary controls is required when the facility being decommissioned contains radiological inventory or contamination exceeding the Rule's definition for low-level residual fixed radioactivity. This document discusses a cost-effective DSA approach that is based on the concepts of DOE-STD-I 120 and meets the 10 CFR 830 safe harbor requirements for both transition surveillance and maintenance as well as decommissioning. This DSA approach provides continuity for inactive Hanford nuclear facilities that will eventually transition into decommissioning. It also uses a graded approach that meets the expectations of DOE-STD-3011 and addresses HAZWOPER requirements to provide a sound basis for worker protection, particularly where intrusive work is being conducted.

JACKSON, M.W.

2002-05-01T23:59:59.000Z

344

Frictional forces in helical buckling of tubing  

SciTech Connect

Previous analyses of helical buckling of tubing have not considered frictional forces. This paper describes the modifications to helical buckling theory necessary to include friction. The first need is a relationship between the buckling force and the casing to tubing contact force. This contact force is determined through use of the principle of virtual work. The next need is the relationship between the friction forces, the buckling force, and the geometry of the tubing helix. Differential equations are derived and solved for two cases of interest: buckling during the landing of the tubing and thermal and differential pressure loading subsequent to landing. Several example problems are examined to evaluate the relative importance of friction.

Mitchell, R.F.

1984-09-01T23:59:59.000Z

345

Impedance tube measurements of printed porous materials  

Science Journals Connector (OSTI)

An impedance tube has been used to make measurements of the acoustic impedance of porous samples. Porous with designed porosities and tortuosities have been produced using 3D printing. Measured impedances are compared to calculated values.

Carl Frederickson

2014-01-01T23:59:59.000Z

346

Sample inlet tube for ion source  

DOE Patents (OSTI)

An improved inlet tube is positioned within an aperture through the device to allow the passage of ions from the ion source, through the improved inlet tube, and into the interior of the device. The inlet tube is designed with a larger end and a smaller end wherein the larger end has a larger interior diameter than the interior diameter of the smaller end. The inlet tube is positioned within the aperture such that the larger end is pointed towards the ion source, to receive ions therefrom, and the smaller end is directed towards the interior of the device, to deliver the ions thereto. Preferably, the ion source utilized in the operation of the present invention is a standard electrospray ionization source. Similarly, the present invention finds particular utility in conjunction with analytical devices such as mass spectrometers.

Prior, David [Hermiston, OR; Price, John [Richland, WA; Bruce, Jim [Oceanside, CA

2002-09-24T23:59:59.000Z

347

Magnetic field lines for a flux tube  

Science Journals Connector (OSTI)

Equations for the magnetic field components in a two dimensional cylindrically symmetric ... in a simple case, solved. The resulting magnetic configuration possesses a strong magnetic field in a thin tube below a...

C. D. C. Steele; Rekha Jain

1993-05-01T23:59:59.000Z

348

Forced-convection condensation inside tubes  

E-Print Network (OSTI)

High vapor velocity condensation inside a tube was studied analytically. The von Karman universal velocity distribution was applied to the condensate flow, pressure drops were calculated using the Lockhart- Martinelli ...

Traviss, Donald P.

1971-01-01T23:59:59.000Z

349

Floor tube corrosion in recovery boilers  

SciTech Connect

Lower sulfur emissions at a pulp mill result in higher sulfidity levels and in the enrichment of potassium in the mill`s liquor system. The sulfidity values at Scandinavian kraft mills previously fluctuated between 28 and 35%; today they exceed 45%. Viscosity measurements show that the viscosity decreases drastically when the sulfidity increases from 30 mole% to 40 mole%, its potassium and chlorine levels are high enough, and the char bed is low, the smelt flows easily and may penetrate the char bed, approaching the floor tubes. In extreme cases, the hot smelt destroys the layer of solidified smelt on the floor tube`s surface and reacts very rapidly with the floor tube.

Klarin, A. [A. Ahistrom Corp., Helsinki (Finland)

1993-12-01T23:59:59.000Z

350

Controlled Thermal-Mechanical Processing of Tubes and Pipes for Enhanced Manufacturing and Performance  

SciTech Connect

The Alloy Steel Business of The Timken Company won an award for the controlled thermo-mechanical processing (CTMP) project and assembled a strong international public/private partnership to execute the project. The premise of the CTMP work was to combine Timken's product understanding with its process expertise and knowledge of metallurgical and deformation fundamentals developed during the project to build a predictive process design capability. The CTMP effort succeeded in delivering a pc-based capability in the tube optimization model, with a virtual pilot plant (VPP) feature to represent the desired tube making process to predict the resultant microstructure tailored for the desired application. Additional tasks included a system for direct, online measurement of grain size and demonstration of application of CTMP via robotically enhanced manufacturing.

Kolarik, Robert V.

2005-11-11T23:59:59.000Z

351

Technology, safety and costs of decommissioning a reference boiling water reactor power station. Volume 2. Appendices. Technical report, September 1977-October 1979  

SciTech Connect

Technology, safety and cost information is given for the conceptual decommissioning of a large (1100MWe) boiling water reactor (BWR) power station. Three approaches to decommissioning, immediate dismantlement, safe storage with deferred dismantlement and entombment, were studied to obtain comparisons between costs, occupational radiation doses, potential dose to the public and other safety impacts. It also shows the sensitivity of decommissioning safety and costs to the power rating of a BWR in the range of 200 to 1100 MWE. This volume contains the appendices.

Oak, H.D.; Holter, G.M.; Kennedy, W.E. Jr.; Konzek, G.J.

1980-06-01T23:59:59.000Z

352

Generalized correlation for foam flow in tubes  

E-Print Network (OSTI)

GENERALIZED CORRELATION FOR FOAM FLOW IN TUBES A Thesis by CAROL LYNNETTE COTTER Submitted to the Office of Graduate Studies of Texas A&M University in partial fulfillment of the requirements for the degree of MASTER OF SCIENCE December.... (December 1996) Carol Lynnette Cotter, B. S. , Texas A&M University Chair of Advisory Committee: Dr. Raymond W. Flumerfelt A novel experimental procedure to determine the behavior of foam flow in tubes is established. Using an approach developed...

Cotter, Carol Lynnette

2012-06-07T23:59:59.000Z

353

Soft pion emission from fat flux tubes  

SciTech Connect

The emission of pions from multiquark flux tubes is examined as an explanation of the soft pion puzzle. Although the soft pion spectra from the decay of fat flux tubes can account for some low {ital p}{sub {perpendicular}} enhancement, the dependence on the number of involved quarks is too weak to provide a plausible explanation of the observed enhancement in the pion spectrum at low transverse momenta.

Kusnezov, D.; Danielewicz, P. (National Superconducting Cyclotron Laboratory and Department of Physics Astronomy, Michigan State University, East Lansing, Michigan (USA))

1991-08-01T23:59:59.000Z

354

Project Year Project Team  

E-Print Network (OSTI)

An Engineer's Guide to the Structures of Baltimore Audience Students from the Krieger School of Arts City, interfaced through a course website, the team will integrate descriptions of structural behavior format. Technologies Used HTML/Web Design, MySQL Project Abstract Structural analysis is typically taught

Gray, Jeffrey J.

355

Project Year Project Team  

E-Print Network (OSTI)

information systems (GIS) tools to design maps that integrate data for visualizing geographic concepts School of Engineering Project Title GIS & Introductory Geography Audience Undergraduate students on how to use the Internet for geographic research, and an interactive introduction to GIS through online

Gray, Jeffrey J.

356

Project Management Project Managment  

E-Print Network (OSTI)

­ Inspired by agile methods #12;Background · Large-scale software development & IT projects, plagued relations #12;One Agile Approach to Scheduling · The creative nature of game development resist heavy up Problems ­incompatible platforms, 3rd party etc. #12;Is Games Development Similar? · Yes & No

Stephenson, Ben

357

Tube construction for fluidized bed combustor  

DOE Patents (OSTI)

A fluidized bed combustor comprises a reactor or a housing which has a windbox distributor plate adjacent the lower end thereof which contains a multiplicity of hole and air discharge nozzles for discharging air and coal into a fluidized bed which is maintained above the distributor plate and below a take-off connection or flue to a cyclone separator in which some of the products of combustion are treated to remove the dust which is returned into the fluidized bed. A windbox is spaced below the fluidized bed and it has a plurality of tubes passing therethrough with the passage of combustion air and fluidizing air which passes through an air space so that fluidizing air is discharged into the reaction chamber fluidized bed at the bottom thereof to maintain the bed in a fluidized condition. A fluid, such as air, is passed through the tubes which extend through the windbox and provide a preheating of the combustion air and into an annular space between telescoped inner and outer tubes which comprise heat exchanger tubes or cooling tubes which extend upwardly through the distributor plate into the fluidized bed. The heat exchanger tubes are advantageously arranged so that they may be exposed in groups within the reactor in a cluster which is arranged within holding rings.

De Feo, Angelo (Totowa, NJ); Hosek, William (Mt. Tabor, NJ)

1984-01-01T23:59:59.000Z

358

Fluidized bed combustor and tube construction therefor  

DOE Patents (OSTI)

A fluidized bed combustor comprises a reactor or a housing which has a windbox distributor plate adjacent the lower end thereof which contains a multiplicity of hole and air discharge nozzles for discharging air and coal into a fluidized bed which is maintained above the distributor plate and below a take-off connection or flue to a cyclone separator in which some of the products of combustion are treated to remove the dust which is returned into the fluidized bed. A windbox is spaced below the fluidized bed and it has a plurality of tubes passing therethrough with the passage of combustion air and fluidizing air which passes through an air space so that fluidizing air is discharged into the reaction chamber fluidized bed at the bottom thereof to maintain the bed in a fluidized condition. A fluid, such as air, is passed through the tubes which extend through the windbox and provide a preheating of the combustion air and into an annular space between telescoped inner and outer tubes which comprise heat exchanger tubes or cooling tubes which extend upwardly through the distributor plate into the fluidized bed. The heat exchanger tubes are advantageously arranged so that they may be exposed in groups within the reactor in a cluster which is arranged within holding rings.

De Feo, Angelo (Passaic, NJ); Hosek, William (Morris, NJ)

1981-01-01T23:59:59.000Z

359

Report to Congress on Plan for Interim Storage of Spent Nuclear Fuel from Decommissioned Reactors  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

6 6 Report to Congress on the Demonstration of the Interim Storage of Spent Nuclear Fuel from Decommissioned Nuclear Power Reactor Sites December 2008 U.S. Department of Energy Office of Civilian Radioactive Waste Management Washington, D.C. Report to Congress on the Demonstration of the Interim Storage of Spent Nuclear Fuel The picture on the cover is the Connecticut Yankee Independent Spent Fuel Storage Installation site in Haddam, Connecticut, with 43 dry storage NRC-licensed dual-purpose (storage and transport) casks. ii Report to Congress on the Demonstration of the Interim Storage of Spent Nuclear Fuel EXECUTIVE SUMMARY The House Appropriations Committee Print that accompanied the Consolidated Appropriations Act, 2008, requests that the U.S. Department of Energy (the Department):

360

DOE-STD-1166-2003; Deactivation and Decommissioning Functional Area Qualification Standard  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

NOT MEASUREMENT SENSITIVE DOE-STD-1166-2003 September 2003 DOE STANDARD DEACTIVATION AND DECOMMISSIONING FUNCTIONAL AREA QUALIFICATION STANDARD DOE Defense Nuclear Facilities Technical Personnel U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-STD-1166-2003 This document has been reproduced directly from the best available copy. Available to DOE and DOE contractors from the Office of Scientific and Technical Information, P.O. Box 62, Oak Ridge, TN 37831; (423) 576-8401. Available to the public from the U.S. Department of Commerce, Technology Administration, National Technical Information Service, Springfield, VA 22161;

Note: This page contains sample records for the topic "tube project decommissioning" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


361

Assessment of the radiological impact of a decommissioning nuclear power plant in Italy  

E-Print Network (OSTI)

The assessment of the radiological impact of a decommissioning Nuclear Power Plant is presented here through the results of an environmental monitoring survey carried out in the area surrounding the Garigliano Power Plant. The levels of radioactivity in soil, water, air and other environmental matrices are shown, in which {\\alpha}, {\\beta} and {\\gamma} activity and {\\gamma} equivalent dose rate are measured. Radioactivity levels of the samples from the Garigliano area are analyzed and then compared to those from a control zone situated more than 100 km away. Moreover, a comparison is made with a previous survey held in 2001. The analyses and comparisons show no significant alteration in the radiological characteristics of the area surroundings the plant, with an overall radioactivity depending mainly from the global fallout and natural sources.

A. Petraglia; C. Sabbarese; M. De Cesare; N. De Cesare; F. Quinto; F. Terrasi; A. D'Onofrio; P. Steier; L. K. Fifield; A. M. Esposito

2012-07-17T23:59:59.000Z

362

Assessment of the radiological impact of a decommissioning nuclear power plant in Italy  

E-Print Network (OSTI)

The assessment of the radiological impact of a decommissioning Nuclear Power Plant is presented here through the results of an environmental monitoring survey carried out in the area surrounding the Garigliano Power Plant. The levels of radioactivity in soil, water, air and other environmental matrices are shown, in which {\\alpha}, {\\beta} and {\\gamma} activity and {\\gamma} equivalent dose rate are measured. Radioactivity levels of the samples from the Garigliano area are analyzed and then compared to those from a control zone situated more than 100 km away. Moreover, a comparison is made with a previous survey held in 2001. The analyses and comparisons show no significant alteration in the radiological characteristics of the area surroundings the plant, with an overall radioactivity depending mainly from the global fallout and natural sources.

Petraglia, A; De Cesare, M; De Cesare, N; Quinto, F; Terrasi, F; D'Onofrio, A; Steier, P; Fifield, L K; Esposito, A M; 10.1051/radiopro/2012010

2012-01-01T23:59:59.000Z

363

Nuclear Rocket Test Facility Decommissioning Including Controlled Explosive Demolition of a Neutron-Activated Shield Wall  

SciTech Connect

Located in Area 25 of the Nevada Test Site, the Test Cell A Facility was used in the 1960s for the testing of nuclear rocket engines, as part of the Nuclear Rocket Development Program. The facility was decontaminated and decommissioned (D&D) in 2005 using the Streamlined Approach For Environmental Restoration (SAFER) process, under the Federal Facilities Agreement and Consent Order (FFACO). Utilities and process piping were verified void of contents, hazardous materials were removed, concrete with removable contamination decontaminated, large sections mechanically demolished, and the remaining five-foot, five-inch thick radiologically-activated reinforced concrete shield wall demolished using open-air controlled explosive demolition (CED). CED of the shield wall was closely monitored and resulted in no radiological exposure or atmospheric release.

Michael Kruzic

2007-09-01T23:59:59.000Z

364

Savannah River Site Removes Dome, Opening Reactor for Recovery Act Decommissioning  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

American Recovery and Reinvestment American Recovery and Reinvestment Act workers achieved a significant milestone in the decommissioning of a Cold War reactor at the Sa- vannah River Site this month after they safely re- moved its rusty, orange, 75-foot-tall dome. With the help of a 660-ton crane and lifting lugs, the work- ers pulled the 174,000-pound dome off the Heavy Water Components Test Reactor, capping more than 16 months of preparations. Workers will cut the dome into smaller pieces for disposal. Removal of the dome allows workers to access the 219,000-pound reactor vessel and two steam generators so they can remove and permanently dispose them onsite. Re- maining equipment will be moved to the cavity vacated by the vessel, and below-grade portions of the reactor will be

365

Source term characterization program for the decommissioning waste from a CANDU reactor  

Science Journals Connector (OSTI)

An automatic source term characterization program was developed, and its structure, logic, and function are explained here in detail. Called the CANDU Activated Source Term Evaluator (CASE), the developed program is equipped with a convenient graphical user interface; it uses MCNP for the neutron transport calculation and ORIGEN2 for activation analysis. CASE can prepare the MCNP input and run MCNP to obtain the neutron flux and the cross section. It can also prepare the ORIGEN2 input for the activation analysis of the region of interest, process the ORIGEN2 output, and compare the estimated specific activity of activated waste with the waste classification standard. CASE is expected to be very useful for reducing the engineering time, minimizing human error, and enhancing the reliability of source term evaluations of decommissioning waste from CANDU reactors.

Dong-Keun Cho; Jeong-Hun Cha; Dong-Hak Kook; Jong-Youl Lee; Heui-Joo Choi; Jongwon Choi; Won-il Ko; Jeong-Ho Park

2012-01-01T23:59:59.000Z

366

Assessment of the Integrated Facility Disposition Project at Oak Ridge  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Assessment of the Integrated Facility Disposition Project at Oak Assessment of the Integrated Facility Disposition Project at Oak Ridge National Laboratory & Y-12 for Transfer of Facilities & Materials to EM Assessment of the Integrated Facility Disposition Project at Oak Ridge National Laboratory & Y-12 for Transfer of Facilities & Materials to EM In December 2007, the Assistant Secretary for Environmental Management (EM-1) invited the DOE Program Secretarial Offices (PSOs) of Nuclear Energy (NE), Science (SC), and the National Nuclear Security Administration (NNSA) to propose facilities and legacy waste for transfer to Environmental Management (EM) for final disposition or deactivation and decommissioning (D&D). Assessment of the Integrated Facility Disposition Project at Oak Ridge National Laboratory & Y-12 for Transfer of Facilities & Materials to EM

367

DEPARTMENT OF ENERGY EERE PROJECT MANAGEMENT CENTER NEPA DETERMINATION  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

.eU) , .eU) , u.s. DEPARTMENT OF ENERGY EERE PROJECT MANAGEMENT CENTER NEPA DETERMINATION RECIPIENT: Parker Hannifin, Aircraft Wheel and Brake Diy PROJECT TITl.E: Wind Turbine Electric Brake project Page 1 of2 STATE: OH Funding Opportunity Announcement Number Pro<:urement Instrument Number NEPA Control Number CID Number COP DE-EEOOOO296 GF0-10-053 0 Based on my review orthe information concerning tbe proposed action, as NEPA Compliance Officer- (autboriztd under DOE Order 4SI.1A), I have made the following determination: ex, EA, [IS APPENDIX AND NUMBER: Description: B3.6 Siting. construction (or modification). operation . and decommissioning of facilities for indoor bench-scale research projects and conventional laboratory operations (for example. preparation of chemical standards and sample analysis):

368

Project Management Plan Examples 1 - 80 | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Project Management Plan Examples 1 - 80 Project Management Plan Examples 1 - 80 Project Management Plan Examples 1 - 80 The following material has been extracted from several project management plans. The order in which it is presented is arbitrary. The descriptions below should be used to navigate to the subject of interest. Policy & Operational Decisions, Assumptions and Strategies - Examples 1 & 2 - Includes organizational responsibilities and structure, disposition path, future use of facility, S&S Reqs and plan, hazard elimination or mitigation, NEPA, RCRA, CERCLA, HVAC/lighting service reqs, structural integrity reqs, etc. Facility End State Decisions - Examples 3, 4 & 5 - Includes expected conditions at completion of the deactivation, DOE mission use, extended S&M, decommissioned and/or dismantled, etc.

369

Assessment of the Integrated Facility Disposition Project at Oak Ridge  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

the Integrated Facility Disposition Project at Oak the Integrated Facility Disposition Project at Oak Ridge National Laboratory & Y-12 for Transfer of Facilities & Materials to EM Assessment of the Integrated Facility Disposition Project at Oak Ridge National Laboratory & Y-12 for Transfer of Facilities & Materials to EM In December 2007, the Assistant Secretary for Environmental Management (EM-1) invited the DOE Program Secretarial Offices (PSOs) of Nuclear Energy (NE), Science (SC), and the National Nuclear Security Administration (NNSA) to propose facilities and legacy waste for transfer to Environmental Management (EM) for final disposition or deactivation and decommissioning (D&D). Assessment of the Integrated Facility Disposition Project at Oak Ridge National Laboratory & Y-12 for Transfer of Facilities & Materials to EM

370

Issues in UK cleanup and decommissioning; a strategic R and D programme  

SciTech Connect

Nexia Solutions is contracted to manage and carry out research on behalf of the Nuclear Decommissioning Authority (NDA). This paper will describe the nuclear research ongoing and how it fits in with the UK cleanup and decommissioning strategy. The aim of the strategic R and D programme is to assist the NDA in maintaining a technical portfolio which will:- - identify and address challenges and clean-up problems that do not have an existing solution; - resolve potential inconsistencies between sites in the technical bases for certain strategic decisions and their implementation; - maintain options while developing strategy (emerging risks); - save costs by developing multi-site solutions; - provide technology, skills and facilities on the timescale required. The strategy for the R and D programme has been developed from a top-level approach by understanding the challenges which need to be addressed and prioritising these according to the objectives of the programme. The programme has demonstrated that a technical portfolio comprising six areas, each containing a number of key themes, is appropriate to address the technical challenges which the NDA faces and aligns with the NDA's technical issues register. An important aspect of the R and D programme is that it should create opportunities for undertaking the NDA mission more effectively. This arises from the emphasis given in those technical programmes which define the challenge more precisely and thus provide a platform from which to produce innovative solutions. The paper will present an overview of the strategic R and D programme along with the key technical programme areas. Examples will be provided of the technical work ongoing, and the results obtained so far. (author)

Tinsley, T.P.; Ashley, V.B.; Morgan, H.G.; Fairhall, G.A. [Nexia Solutions, British Technology Centre, Sellafield, Seascale, Cumbria (United Kingdom)

2008-07-01T23:59:59.000Z

371

Project Accounts  

NLE Websites -- All DOE Office Websites (Extended Search)

» Project Accounts » Project Accounts Project Accounts Overview Project accounts are designed to facilitate collaborative computing by allowing multiple users to use the same account. All actions performed by the project account are traceable back to the individual who used the project account to perform those actions via gsisshd accounting logs. Requesting a Project Account PI's, PI proxies and project managers are allowed to request a project account. In NIM do "Actions->Request a Project Account" and fill in the form. Select the repository that the Project Account is to use from the drop-down menu, "Sponsoring Repository". Enter the name you want for the account (8 characters maximum) and a description of what you will use the account for and then click on the "Request Project Account" button. You

372

Project Fact Sheet Project Update  

E-Print Network (OSTI)

Project Fact Sheet Project Update: Project Brief: A state of the art facility, at Hammersmith information visit the Faculty of Medicine web pages http://www1.imperial.ac.uk/medicine/ Construction Project Team: Project Facts & Figures: Budget: £60 000 000 Funding Source: SRIF II (Imperial College), GSK, MRC

373

Project Fact Sheet Project Update  

E-Print Network (OSTI)

Project Fact Sheet Project Update: Project Brief: The refurbishment of the instrumentation equipment. This project encompasses refurbishment work on over 1,150m2 of laboratory space across four, the completed project will allow researchers to expand their work in satellite instrumentation, the fabrication

374

Project Fact Sheet Project Brief  

E-Print Network (OSTI)

Project Fact Sheet Project Brief: In the first phase of the Union Building re.union.ic.ac.uk/marketing/building Construction Project Team: Project Facts & Figures: Budget: £1,400,000 Funding Source: Capital Plan and Imperial College Union reserves Construction Project Programme: Start on Site: August 2006 End Date: March

375

Evaluation of nuclear facility decommissioning projects: Summary status report: Three Mile Island Unit 2. Radioactive waste and laundry shipments  

SciTech Connect

This document summarizes information concerning radioactive waste and laundry shipments from the Three Mile Island Nuclear Station Unit 2 to radioactive waste disposal sites and to protective clothing decontamination facilities (laundries) since the loss of coolant accident experienced on March 28, 1979. Data were collected from radioactive shipment records, summarized, and placed in a computerized data information retrieval/manipulation system which permits extraction of specific information. This report covers the period of April 9, 1979 through April 19, 1987. Included in this report are: waste disposal site locations, dose rates, curie content, waste description, container type and number, volumes and weights. This information is presented in two major categories: protective clothing (laundry) and radioactive waste. Each of the waste shipment reports is in chronological order.

Doerge, D. H.; Haffner, D. R.

1988-06-01T23:59:59.000Z

376

Evaluation of nuclear facility decommissioning projects. Three Mile Island Unit 2 reactor defueling and disassembly. Summary status report. Volume 3  

SciTech Connect

This document summarizes information relating to the preparations for defueling the Three Mile Island Unit 2 (TMI-2) reactor and disassembly activities being performed concurrently with decontamination of the facility. Data have been collected from activity reports, reactor containment entry records, and other sources and entered in a computerized data sysem which permits extraction/manipulation of specific data which can be used in planning for recovery from a loss of coolant event similar to that experienced at TMI-2 on March 28, 1979. This report contains summaries of man-hours, manpower, and radiation exposures incurred during the period of April 23, 1979 to April 16, 1985, in the completion of activities related to preparation for reactor defueling. Support activities conducted outside of radiation areas are not included within the scope of this report. Computerized reports included in this document are: A chronological summary listing work performed for the period; and summary reports for each major task undertaken in connection with the specific scope of this report. Presented in chronological order for the referenced time period. Manually-assembled table summaries are included for: Labor and exposures by department; and labor and exposures by major activity.

Doerge, D.H.; Miller, R.L.; Scotti, K.S.

1986-05-01T23:59:59.000Z

377

Evaluation of nuclear facility decommissioning projects. Three Mile Island Unit 2 reactor building decontamination. Summary status report. Volume 2  

SciTech Connect

This document summarizes information relating to decontamination of the Three Mile Island Unit 2 (TMI-2) reactor building. The report covers activities for the period of June 1, 1979 through March 29, 1985. The data collected from activity reports, reactor containment entry records, and other sources were entered into a computerized data system which permits extraction/manipulation of specific information which can be used in planning for recovery from an accident similar to that experienced at TMI-2 on March 28, 1979. This report contains summaries of man-hours, manpower, and radiation exposures incurred during decontamination of the reactor building. Support activities conducted outside of radiation areas are excluded from the scope of this report. Computerized reports included in this document are: a chronological summary listing work performed relating to reactor building decontamination for the period specified; and summary reports for each major task during the period. Each task summary is listed in chronological order for zone entry and subtotaled for the number of personnel entries, exposures, and man-hours. Manually-assembled table summaries are included for: labor and exposures by department and labor and exposures by major activity.

Doerge, D.H.; Miller, R.L.; Scotti, K.S.

1986-05-01T23:59:59.000Z

378

Method of positioning tubing within a horizontal well  

SciTech Connect

This patent describes a method of variably and selectively positioning coil tubing in a horizontally drilled well having a generally vertical section, a curve section and a generally horizontal section. It comprises securing a generally hollow tubing guide shoe to one end of a tubing string; inserting the tubing guide shoe and a portion of the tubing string through the generally vertical section and the curve section and into a portion of the generally horizontal section; and inserting coil tubing through the tubing string.

Young, C.E.

1992-06-02T23:59:59.000Z

379

Volume Project  

E-Print Network (OSTI)

Math 13900. Volume Project. For the following project, you may use any materials. This must be your own original creation. Construct a right pyramid with a base ...

rroames

2010-01-12T23:59:59.000Z

380

Fireside carburization of stainless steel furnace tubes  

SciTech Connect

Most heavy Venezuelan crudes are recognized for having a high total acid number (TAN) that is usually associated with a high tendency to produce naphthenic acid corrosion. To resist this type of corrosion in vacuum heaters, 9Cr-1Mo steel and stainless steels containing molybdenum are usually recommended. In 1993 the original 5Cr-1/2Mo roof tubes of the furnace in a vacuum unit were replaced by stainless steel 316Ti to minimize tube replacement and increase heater reliability. Unexpectedly, some of the new tubes failed after only three years of service, and just one year after undergoing the last turnaround inspection. The damage occurred in the form of deep holes and perforations, starting from the outside tube surface on the fireside. Coke build-up occurred due to severe operating conditions, overheating the tubes on the fireside, above 675 C (1250 F). Metallographic and Scanning Electron Microscopic (SEM) examination revealed internal and external carburization of the material due to the presence of coke and combustion ashes, respectively. The increase in the skin metal temperature facilitated the diffusion of carbon from these carbon-rich deposits into the low carbon content material (0.023 O/O).Depletion of chromium at the grain boundaries due to the massive formation of chromium carbides, resulted in a severe intergranular corrosion attack by molten salts rich in vanadium and sulfur due to asphalt burning. Normal operating practice demands the use of steam for the heater tubes to control coke build-up. This practice had been first reduced and then eliminated, during the past two years prior to the failure, because of economic incentives. This paper describes the root cause analysis conducted to account for these premature tube failures.

Mirabal, E.; Molina, C. [PDVSA-Refineria Isla, Curayao (Netherlands); Mayorga, A.; Hau, J.L. [PDVSA-Intevep, Caracas (Venezuela)

1999-11-01T23:59:59.000Z

Note: This page contains sample records for the topic "tube project decommissioning" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


381

Estimating boiling water reactor decommissioning costs. A user`s manual for the BWR Cost Estimating Computer Program (CECP) software: Draft report for comment  

SciTech Connect

With the issuance of the Decommissioning Rule (July 27, 1988), nuclear power plant licensees are required to submit to the U.S. Regulatory Commission (NRC) for review, decommissioning plans and cost estimates. This user`s manual and the accompanying Cost Estimating Computer Program (CECP) software provide a cost-calculating methodology to the NRC staff that will assist them in assessing the adequacy of the licensee submittals. The CECP, designed to be used on a personal computer, provides estimates for the cost of decommissioning BWR power stations to the point of license termination. Such cost estimates include component, piping, and equipment removal costs; packaging costs; decontamination costs; transportation costs; burial costs; and manpower costs. In addition to costs, the CECP also calculates burial volumes, person-hours, crew-hours, and exposure person-hours associated with decommissioning.

Bierschbach, M.C. [Pacific Northwest Lab., Richland, WA (United States)

1994-12-01T23:59:59.000Z

382

EIS-0259: Disposal of Decommissioned, Defueled Cruiser, Ohio Class and Los Angeles Class Naval Reactor Plants, Hanford Site, Richland (adopted from Navy)  

Energy.gov (U.S. Department of Energy (DOE))

This EIS analyzes the alternate ways for disposing of decommissioned, defieled reactor compliments from U.S. Navy nuclear-powered cruisers, (Bainbridge, Truxtun, Long Beach, California Class and Virginia Class) and Los Angeles Class, and Ohio Class submarines.

383

Project 106  

NLE Websites -- All DOE Office Websites (Extended Search)

Single Large Format Single Large Format Tube Tester Large Format OTM Tubes Multi-tube Pilot Plant Reactor, P-1 DEVELOPMENT OF OXYGEN TRANSPORT MEMBRANE (OTM) FOR PRODUCTION AND TESTING OF SYNTHESIS GAS-DERIVED ULTRA-CLEAN FUELS Description Natural gas is an attractive feedstock for the production of ultra-clean fuels (UCF) because it is abundant and inexpensive, and can be converted into a number of sulfur free fuels including diesel, gasoline, dimethyl ether and derivatives, methanol and other oxygenates that can be used within the existing fuel distribution infrastructure. These fuels, when used neat, or when blended with petroleum based fuels, have the potential to dramatically reduce vehicle emissions from a number of propulsion systems including advanced IC (internal combustion) engines, fuel cells, and IC- fuel cell hybrids.

384

The U-tube sampling methodology and real-time analysis of geofluids  

SciTech Connect

The U-tube geochemical sampling methodology, an extension of the porous cup technique proposed by Wood [1973], provides minimally contaminated aliquots of multiphase fluids from deep reservoirs and allows for accurate determination of dissolved gas composition. The initial deployment of the U-tube during the Frio Brine Pilot CO{sub 2} storage experiment, Liberty County, Texas, obtained representative samples of brine and supercritical CO{sub 2} from a depth of 1.5 km. A quadrupole mass spectrometer provided real-time analysis of dissolved gas composition. Since the initial demonstration, the U-tube has been deployed for (1) sampling of fluids down gradient of the proposed Yucca Mountain High-Level Waste Repository, Armagosa Valley, Nevada (2) acquiring fluid samples beneath permafrost in Nunuvut Territory, Canada, and (3) at a CO{sub 2} storage demonstration project within a depleted gas reservoir, Otway Basin, Victoria, Australia. The addition of in-line high-pressure pH and EC sensors allows for continuous monitoring of fluid during sample collection. Difficulties have arisen during U-tube sampling, such as blockage of sample lines from naturally occurring waxes or from freezing conditions; however, workarounds such as solvent flushing or heating have been used to address these problems. The U-tube methodology has proven to be robust, and with careful consideration of the constraints and limitations, can provide high quality geochemical samples.

Freifeld, Barry; Perkins, Ernie; Underschultz, James; Boreham, Chris

2009-03-01T23:59:59.000Z

385

Project Controls  

Directives, Delegations, and Requirements

Project controls are systems used to plan, schedule, budget, and measure the performance of a project/program. The cost estimation package is one of the documents that is used to establish the baseline for project controls. This chapter gives a brief description of project controls and the role the cost estimation package plays.

1997-03-28T23:59:59.000Z

386

Power Tube Inc | Open Energy Information  

Open Energy Info (EERE)

Power Tube Inc Power Tube Inc Jump to: navigation, search Name Power Tube Inc Place Houston, Texas Zip 77060 Sector Geothermal energy Product Texan geothermal systems developer. Has developed a new range of geothermal heat exchangers from biodegradable materials. Coordinates 29.76045°, -95.369784° Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"ROADMAP","zoom":14,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"600px","height":"350px","centre":false,"title":"","label":"","icon":"","visitedicon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"wmsoverlay":"","layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","locations":[{"text":"","title":"","link":null,"lat":29.76045,"lon":-95.369784,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

387

Alternate Materials for Recovery Boiler Superheater Tubes  

SciTech Connect

The ever escalating demands for increased efficiency of all types of boilers would most sensibly be realized by an increase in the steam parameters of temperature and pressure. However, materials and corrosion limitations in the steam generating components, particularly the superheater tubes, present major obstacles to boiler designers in achieving systems that can operate under the more severe conditions. This paper will address the issues associated with superheater tube selection for many types of boilers; particularly chemical recovery boilers, but also addressing the similarities in issues for biomass and coal fired boilers. It will also review our recent study of materials for recovery boiler superheaters. Additional, more extensive studies, both laboratory and field, are needed to gain a better understanding of the variables that affect superheater tube corrosion and to better determine the best means to control this corrosion to ultimately permit operation of recovery boilers at higher temperatures and pressures.

Keiser, James R [ORNL; Kish, Joseph [McMaster University; Singbeil, Douglas [FPInnovations

2009-01-01T23:59:59.000Z

388

Biaxial creep behavior of textured zircaloy tubing  

SciTech Connect

This paper reports on zirconium alloys which are commonly used in light-water reactors as thin-walled tubing to clad highly radioactive fuel. The tubes experience varied stresses at high temperatures while being exposed to high-neutron radiation, resulting in thermal creep and radiation growth and creep. However, the dimensional stability of these materials is important to preventing leakage of fission gases and contamination of the coolant water. Predicting the dimensional changes of the thin-walled tubes is further complicated by the anisotropic nature of the hexagonal close-packaged metals. This article summarizes the procedures used in the texture analyses and crystal plasticity in developing model equations to predict the dimensional changes of Zircaloy fuel cladding, both out-of-pile and in-reactor. These methodologies can be extended to the life prediction of these important structures in nuclear reactors.

Murty, L.K. (North Carolina State Univ., NC (US))

1992-02-01T23:59:59.000Z

389

Field Demonstraton of Existing Microhole Coiled Tubing Rig (MCTR) Technology  

SciTech Connect

The performance of an advanced Microhole Coiled Tubing Rig (MCTR) has been measured in the field during the drilling of 25 test wells in the Niobrara formation of Western Kansas and Eastern Colorado. The coiled tubing (CT) rig designed, built and operated by Advanced Drilling Technologies (ADT), was documented in its performance by GTI staff in the course of drilling wells ranging in depth from 500 to nearly 3,000 feet. Access to well sites in the Niobrara for documenting CT rig performance was provided by Rosewood Resources of Arlington, VA. The ADT CT rig was selected for field performance evaluation because it is one of the most advanced commercial CT rig designs that demonstrate a high degree of process integration and ease of set-up and operation. Employing an information collection protocol, data was collected from the ADT CT rig during 25 drilling events that encompassed a wide range of depths and drilling conditions in the Niobrara. Information collected included time-function data, selected parametric information indicating CT rig operational conditions, staffing levels, and field observations of the CT rig in each phase of operation, from rig up to rig down. The data obtained in this field evaluation indicates that the ADT CT rig exhibited excellent performance in the drilling and completion of more than 25 wells in the Niobrara under varied drilling depths and formation conditions. In the majority of the 25 project well drilling events, ROP values ranged between 300 and 620 feet per hour. For all but the lowest 2 wells, ROP values averaged approximately 400 feet per hour, representing an excellent drilling capability. Most wells of depths between 500 and 2,000 feet were drilled at a total functional rig time of less than 16 hours; for wells as deep at 2,500 to 3,000 feet, the total rig time for the CT unit is usually well under one day. About 40-55 percent of the functional rig time is divided evenly between drilling and casing/cementing. The balance of time is divided among the remaining four functions of rig up/rig down, logging, lay down bottomhole assembly, and pick up bottomhole assembly. Observations made during all phases of CT rig operation at each of the project well installations have verified a number of characteristics of the technology that represent advantages that can produce significant savings of 25-35 percent per well. Attributes of the CT rig performance include: (1) Excellent hole quality with hole deviation amounting to 1-2 degrees; (2) Reduced need for auxiliary equipment; (3) Efficient rig mobilization requiring only four trailers; (4) Capability of ''Zero Discharge'' operation; (5) Improved safety; and, (6) Measurement while drilling capability. In addition, commercial cost data indicates that the CT rig reduces drilling costs by 25 to 35% compared to conventional drilling technology. Widespread commercial use of the Microhole Coiled Tubing technology in the United States for onshore Lower-48 drilling has the potential of achieving substantially positive impacts in terms of savings to the industry and resource expansion. Successfully commercialized Microhole CT Rig Technology is projected to achieve cumulative savings in Lower-48 onshore drilling expenditures of approximately 6.8 billion dollars by 2025. The reduced cost of CT microhole drilling is projected to enable the development of gas resources that would not have been economic with conventional methods. Because of the reduced cost of drilling achieved with CT rig technology, it is estimated that an additional 22 Tcf of gas resource will become economic to develop. In the future, the Microhole Coiled Tubing Rig represents an important platform for the continued improvement of drilling that draws on a new generation of various technologies to achieve goals of improved drilling cost and reduced impact to the environment.

Kent Perry; Samih Batarseh; Sheriff Gowelly; Thomas Hayes

2006-05-09T23:59:59.000Z

390

Project Hindsight  

Science Journals Connector (OSTI)

...and extended the life of the engine com-pared...blades employed in the turbine engine-that drives...1943, to prevent gas "clean-up" due...compensate for the residual hydrogen clean-up...study of the hydrogen gas discharge and its ef-fect on tube life, were able to develop...

Chalmers W. Sherwin; Raymond S. Isenson

1967-06-23T23:59:59.000Z

391

Information on Hydrologic Conceptual Models, Parameters, Uncertainty Analysis, and Data Sources for Dose Assessments at Decommissioning Sites  

SciTech Connect

This report addresses issues related to the analysis of uncertainty in dose assessments conducted as part of decommissioning analyses. The analysis is limited to the hydrologic aspects of the exposure pathway involving infiltration of water at the ground surface, leaching of contaminants, and transport of contaminants through the groundwater to a point of exposure. The basic conceptual models and mathematical implementations of three dose assessment codes are outlined along with the site-specific conditions under which the codes may provide inaccurate, potentially nonconservative results. In addition, the hydrologic parameters of the codes are identified and compared. A methodology for parameter uncertainty assessment is outlined that considers the potential data limitations and modeling needs of decommissioning analyses. This methodology uses generic parameter distributions based on national or regional databases, sensitivity analysis, probabilistic modeling, and Bayesian updating to incorporate site-specific information. Data sources for best-estimate parameter values and parameter uncertainty information are also reviewed. A follow-on report will illustrate the uncertainty assessment methodology using decommissioning test cases.

Meyer, Philip D.; Gee, Glendon W.; Nicholson, Thomas J.

2000-02-28T23:59:59.000Z

392

Allowable residual contamination levels for decommissioning the 115-F and 117-F facilities at the Hanford Site  

SciTech Connect

This report contains the results of a study sponsored by UNC Nuclear Industries to determine Allowable Residual Contamination Levels (ARCL) for the 115-F and 117-F facilities at the Hanford Site. The purpose of this study is to provide data useful to UNC engineers in conducting safety and cost comparisons for decommissioning alternatives. The ARCL results are based on a scenario/exposure-pathway analysis and compliance with an annual dose limit for three specific modes of future use of the land and facilities. These modes of use are restricted, controlled, and unrestricted. Information on restricted and controlled use is provided to permit a full consideration of decommissioning alternatives. Procedures are presented for modifying the ARCL values to accommodate changes in the radionuclide mixture or concentrations and to determine instrument responses for various mixtures of radionuclides. Finally, a comparison is made between existing decommissioning guidance and the ARCL values calculated for unrestricted release of the 115-F and 117-F facilities. The comparison shows a good agreement.

Kennedy, W.E. Jr.; Napier, B.A.

1983-07-01T23:59:59.000Z

393

DEPARTMENT OF ENERGY EERE PROJECT MANAGEMENT CENTER NEPA DETERM  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

s, s, DEPARTMENT OF ENERGY EERE PROJECT MANAGEMENT CENTER NEPA DETERM INATION RECIPIENT:University of Central Florida PROJECf TITLE : Florida Hydrogen Initiative· 3 letter of Interest (LOI) Projects Page I of2 STATE: Fl Funding Opportunity Announcement Number Procurement Instrument Number NEPA Control Number em Number COP Renewal DE·FC36-04G014225 GF0-04-221e G014225 Based on my review orlbe information concerning the proposed action, as NEPA Compliance Officer (authorized under DOE Order 4S1.IA), I have made the (ollowing determination: ex, EA, EIS APPENDIX AND NUMBER: Description: B 3.6 Siting. construction (or modification). operation, and decommissioning of facilities for indoor bench-scale research projects and conventional laboratory operations (for example, preparation of chemical standards and sample analysis):

394

NE-20 ACTION: SSDP Project Charter Revision CONCURRENCES RTG SYMBOL  

Office of Legacy Management (LM)

0 0 ACTION: SSDP Project Charter Revision CONCURRENCES RTG SYMBOL James W. Vaughan, Jr. N-923 Acting Assistant Secretary . for Nuclear Energy Murphi Attached for your signature is a revised Project Charter for the 1/ 86 Shippingport Station Decommissioning Project (SSDP). Since our original M determination in July that there was a need to revise the SSDP Charter, we N K23 have been in discussion with the Richland Operations Field Office (RL). INe Significant differences in management philosophy surfaced between RL and DeLaney Headquarters that required discussions up to and including the RL Manager DAE/86 and myself. I now feel that the revised Charter reflects a mutually acceptable working arrangement between the appropriate organizations. The RTGSYMBOL general roles and responsibilities defined in this Charter will facilitate

395

EIS-0470 - Cape Wind Energy Project - 2010 - Environmental Assessment  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Wind Energy Project Wind Energy Project Environmental Assessment April 28, 2010 4 OCS EIS/EA MMS 2010-011 FINDING OF NO NEW SI GNIFICANT IMPACT (FO:NNSJ) Issuance of Lease for Offshore Wind Power Facility in Nantucket Sound, Offshore Massachusetts In January 2009, the U.S. Department of the Interior, Minerals Management Service (MMS) prepared and filed with the U.S. Environmental Protection Agency (USEP A) a Final Environmental Impact Statement (FEIS) covering the construction, operation, and decommissioning of the proposed Cape Wind Energy Project, an offshore wind power facility consisting of 130, 3.6± megawatt (MW) wind turbine generators (WTGs), each with a maximum blade height of 440 feet, to be arranged in a grid pattern on the Outer Continental Shelf (OCS) in

396

DEPARTlVffiNT OF ENERGY ~' EERE PROJECT MANAGEMENT CENTER  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Page 1 of2 u.s. DEPARTlVffiNT OF ENERGY ~' EERE PROJECT MANAGEMENT CENTER '~ ' . . NEPA DETElUttllNATION ~ RECIPIENT: Abengoa Solar Inc STATE: eo PROJECT Development of Advanced Polymeric Reflector for esp Applications TITLE: Funding Opportunity Announcement Number Procurement Instrument Number NEPA Control Number CID Number DE-PS36-07G097028 DE-FC36-08G018036 gfo-g018036-004 G018036 Based on my review of the information concerning the proposed action, as NEPA Compliance Officer (authorized under DOE Order 45 1.1 A), I have made the following determination: CX, EA, EIS APPENDIX AND NUMBER: Description: 83.6 Siting, construction (or modification), operation, and decommissioning of facilities for indoor bench-scale research projects and conventional laboratory operations (for example, preparation of chemical standards and sample analysis);

397

Facility Decontamination and Decommissioning Program Surveillance and Maintenance Plan, Revision 2  

SciTech Connect

This Surveillance and Maintenance (S&M) Plan describes the activities performed between deactivation and final decommissioning of the following facilities located on the Nevada National Security Site, as documented in the Federal Facility Agreement and Consent Order under the Industrial Sites program as decontamination and decommissioning sites: ? Engine Maintenance, Assembly, and Disassembly (EMAD) Facility: o EMAD Building (Building 25-3900) o Locomotive Storage Shed (Building 25-3901) ? Test Cell C (TCC) Facility: o Equipment Building (Building 25-3220) o Motor Drive Building (Building 25-3230) o Pump Shop (Building 25-3231) o Cryogenic Lab (Building 25-3232) o Ancillary Structures (e.g., dewars, water tower, piping, tanks) These facilities have been declared excess and are in various stages of deactivation (low-risk, long-term stewardship disposition state). This S&M Plan establishes and implements a solid, cost-effective, and balanced S&M program consistent with federal, state, and regulatory requirements. A graded approach is used to plan and conduct S&M activities. The goal is to maintain the facilities in a safe condition in a cost-effective manner until their final end state is achieved. This plan accomplishes the following: ? Establishes S&M objectives and framework ? Identifies programmatic guidance for S&M activities to be conducted by National Security Technologies, LLC, for the U.S. Department of Energy, National Nuclear Security Administration Nevada Field Office (NNSA/NFO) ? Provides present facility condition information and identifies hazards ? Identifies facility-specific S&M activities to be performed and their frequency ? Identifies regulatory drivers, NNSA/NFO policies and procedures, and best management practices that necessitate implementation of S&M activities ? Provides criteria and frequencies for revisions and updates ? Establishes the process for identifying and dispositioning a condition that has not been previously identified or documented ? Provides instructions for implementing annual S&M inspections and activities The following facilities that were included in Revision 1 of this plan have reached final disposition and are no longer in the S&M program: ? Reactor Maintenance, Assembly, and Disassembly Facility, Building 25-3110 ? Test Cell A Facility, Building 25-3113 ? TCC Facility, Building 25-3210 ? Pluto Disassembly Facility, Building 26-2201 ? Super Kukla Facility, Building 27-5400

Poderis, Reed J. [NSTec] [NSTec; King, Rebecca A. [NSTec] [NSTec

2013-09-30T23:59:59.000Z

398

Microhole High-Pressure Jet Drill for Coiled Tubing  

SciTech Connect

Tempress Small Mechanically-Assisted High-Pressure Waterjet Drilling Tool project centered on the development of a downhole intensifier (DHI) to boost the hydraulic pressure available from conventional coiled tubing to the level required for high-pressure jet erosion of rock. We reviewed two techniques for implementing this technology (1) pure high-pressure jet drilling and (2) mechanically-assisted jet drilling. Due to the difficulties associated with modifying a downhole motor for mechanically-assisted jet drilling, it was determined that the pure high-pressure jet drilling tool was the best candidate for development and commercialization. It was also determined that this tool needs to run on commingled nitrogen and water to provide adequate downhole differential pressure and to facilitate controlled pressure drilling and descaling applications in low pressure wells. The resulting Microhole jet drilling bottomhole assembly (BHA) drills a 3.625-inch diameter hole with 2-inch coil tubing. The BHA consists of a self-rotating multi-nozzle drilling head, a high-pressure rotary seal/bearing section, an intensifier and a gas separator. Commingled nitrogen and water are separated into two streams in the gas separator. The water stream is pressurized to 3 times the inlet pressure by the downhole intensifier and discharged through nozzles in the drilling head. The energy in the gas-rich stream is used to power the intensifier. Gas-rich exhaust from the intensifier is conducted to the nozzle head where it is used to shroud the jets, increasing their effective range. The prototype BHA was tested at operational pressures and flows in a test chamber and on the end of conventional coiled tubing in a test well. During instrumented runs at downhole conditions, the BHA developed downhole differential pressures of 74 MPa (11,000 psi, median) and 90 MPa (13,000 psi, peaks). The median output differential pressure was nearly 3 times the input differential pressure available from the coiled tubing. In a chamber test, the BHA delivered up to 50 kW (67 hhp) hydraulic power. The tool drilled uncertified class-G cement samples cast into casing at a rate of 0.04 to 0.17 m/min (8 to 33 ft/hr), within the range projected for this tool but slower than a conventional PDM. While the tool met most of the performance goals, reliability requires further improvement. It will be difficult for this tool, as currently configured, to compete with conventional positive displacement downhole motors for most coil tubing drill applications. Mechanical cutters on the rotating nozzle head would improve cutting. This tool can be easily adapted for well descaling operations. A variant of the Microhole jet drilling gas separator was further developed for use with positive displacement downhole motors (PDM) operating on commingled nitrogen and water. A fit-for-purpose motor gas separator was designed and yard tested within the Microhole program. Four commercial units of that design are currently involved in a 10-well field demonstration with Baker Oil Tools in Wyoming. Initial results indicate that the motor gas separators provide significant benefit.

Ken Theimer; Jack Kolle

2007-06-30T23:59:59.000Z

399

PMC.EF2a U.S. DEPARTMENT OF ENERGY EERE PROJECT MANAGEMENT CENTER  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

U.S. DEPARTMENT OF ENERGY U.S. DEPARTMENT OF ENERGY EERE PROJECT MANAGEMENT CENTER NEPA DE TERARNATION RECIPIENT:Cedar Falls Utilities STATE: IA PROJECT TITLE : Biomass Energy Generation Project Funding Opportunity Announcement Number Procurement Instrument Number NEPA Control Number CID Number CDP DE-EE0000398 GFO-10-035 0 Based on my review of the information concerning the proposed action, as NEPA Compliance Officer (authorized under DOE Order 451.IA), I have made the following determination: CX, EA, EIS APPENDIX AND NUMBER: Description: B3.6 Siting, construction (or modification), operation, and decommissioning of facilities for indoor bench-scale research projects and conventional laboratory operations (for example, preparation of chemical standards and sample analysis); small-scale research and development projects; and small-scale pilot projects (generally less than two years) conducted

400

Digital radiographic systems detect boiler tube cracks  

SciTech Connect

Boiler water wall leaks have been a major cause of steam plant forced outages. But conventional nondestructive evaluation techniques have a poor track record of detecting corrosion fatigue cracking on the inside surface of the cold side of waterwall tubing. EPRI is performing field trials of a prototype direct-digital radiographic system that promises to be a game changer. 8 figs.

Walker, S. [EPRI, Charlotte, NC (United States)

2008-06-15T23:59:59.000Z

Note: This page contains sample records for the topic "tube project decommissioning" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


401

Remote Opening and Sealing of Metal Tubes  

Science Journals Connector (OSTI)

``One?shot'' methods of opening and sealing metal tubes are described. These methods were developed for taking high altitude atmospheric samples in metal bottles carried aloft by rockets and are performed by pyrotechnic means. The sealing is done by cold welding.

L. T. Loh; H. W. Neill; M. H. Nichols; E. A. Wenzel

1952-01-01T23:59:59.000Z

402

"Fine grain Nb tube for SRF cavities"  

SciTech Connect

Superconducting radio frequency (SRF) cavities used in charged particle linear accelerators, are currently fabricated by deep drawing niobium sheets and welding the drawn dishes together. The Nb sheet has a non-uniform microstructure, which leads to unpredictable cavity shape and surface roughness, and inconsistent "spring-back" during forming. In addition, weld zones cause hot spots during cavity operation. These factors limit linear accelerator performance and increase cavity manufacturing cost. Equal channel angular extrusion (ECAE) can be used to refine and homogenize the microstructure of Nb tube for subsequent hydroforming into SRF cavities. Careful selection of deformation and heat treatment conditions during the processing steps can give a uniform and consistent microstructure in the tube, leading to improved deformability and lower manufacturing costs. Favorable microstructures were achieved in short test samples of RRR Nb tube, which may be particularly suitable for hydroforming into SRF cavity strings. The approach demonstrated could be applicable to microstructure engineering of other tube materials including tantalum, titanium, and zirconium.

Robert E. Barber

2012-07-08T23:59:59.000Z

403

Implementation of 10 CFR 20.1406 Through Life Cycle Planning for Decommissioning  

SciTech Connect

This paper summarizes a regulatory guide that the U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, is currently developing for use in implementing Title 10, Section 20.1406, of the Code of Federal Regulations (10 CFR 20.1406), 'Minimization of Contamination'. The intent of the regulation is to diminish the occurrence and severity of 'legacy sites' by taking measures to reduce and control contamination and facilitate eventual decommissioning. The thrust of the regulatory guide is to encourage applicants to use technically sound engineering judgment and a practical risk-informed approach to achieve the objectives of 10 CFR 20.1406. In particular, such an approach should consider the materials and processes involved (e.g., solids, liquids, gases), and focus on (1) the relative significance of potential contamination, (2) areas that are most susceptible to leaks, and (3) the appropriate level of consideration that should be incorporated in facility design and operational procedures to prevent and control contamination. (authors)

O'Donnell, E.; Ott, W.R. [Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, Washington, DC (United States)

2008-07-01T23:59:59.000Z

404

Technical program plan for the transitioning, decommissioning, and final disposition focus area  

SciTech Connect

Hundreds of aging nuclear materials processing facilities within the Department of Energy`s (DOE) Weapons Complex are now being shut down and deactivated. These facilities, situated throughout the United States, will require a monumental effort to clean up safely and with minimal environmental insult. Current cleanup technologies tend to be labor intensive and expensive, they produce an unacceptably large volume of waste, and they expose workers to radioactive and other hazardous substances. This document describes an emerging program designed to develop and demonstrate new technical approaches to the decontamination and decommissioning (D&D) program for DOE`s nuclear materials processing facilities. Sponsored by the DOE Office of Technology Development within the Office of Environmental Restoration and Waste Management (EM), the program seeks to integrate the strengths of DOE`s technical, managerial, and systems engineering capabilities with those of industry, universities, and other government agencies. Once developed, these technologies will help to provide US industry with a competitive edge in the worldwide market that exists for improved environmental restoration and D&D services.

Not Available

1994-01-01T23:59:59.000Z

405

Alum Innovative Exploration Project Geothermal Project | Open Energy  

Open Energy Info (EERE)

Innovative Exploration Project Geothermal Project Innovative Exploration Project Geothermal Project Jump to: navigation, search Last modified on July 22, 2011. Project Title Alum Innovative Exploration Project Project Type / Topic 1 Recovery Act: Geothermal Technologies Program Project Type / Topic 2 Validation of Innovative Exploration Technologies Project Description Phase 1 exploration will consist of two parts: 1) surface and near surface investigations and 2) subsurface geophysical surveys and modeling. The first part of Phase 1 includes: a hyperspectral imaging survey (to map thermal anomalies and geothermal indicator minerals), shallow (6 ft) temperature probe measurements, and drilling of temperature gradient wells to depths of 1000 feet. In the second part of Phase 1, 2D & 3D geophysical modeling and inversion of gravity, magnetic, and magnetotelluric datasets will be used to image the subsurface. This effort will result in the creation of a 3D model composed of structural, geological, and resistivity components. The 3D model will then be combined with the temperature and seismic data to create an integrated model that will be used to prioritize drill target locations. Four geothermal wells will be drilled and geologically characterized in Phase 2. The project will use a coiled-tube rig to test this drilling technology at a geothermal field for the first time. Two slimwells and two production wells will be drilled with core collected and characterized in the target sections of each well. In Phase 3, extended flow tests will be conducted on the producible wells to confirm the geothermal resource followed by an overall assessment of the productivity of the Alum geothermal area. Finally, Phase 3 will evaluate the relative contribution of each exploration technique in reducing risk during the early stages of the geothermal project.

406

Science Projects  

NLE Websites -- All DOE Office Websites (Extended Search)

Argonne Argonne Science Project Ideas! Our Science Project section provides you with sample classroom projects and experiments, online aids for learning about science, as well as ideas for Science Fair Projects. Please select any project below to continue. Also, if you have an idea for a great project or experiment that we could share, please click our Ideas page. We would love to hear from you! Science Fair Ideas Science Fair Ideas! The best ideas for science projects are learning about and investigating something in science that interests you. NEWTON has a list of Science Fair linkd that can help you find the right topic. Toothpick Bridge Web Sites Toothpick Bridge Sites! Building a toothpick bridge is a great class project for physics and engineering students. Here are some sites that we recommend to get you started!

407

Projection Systems  

Science Journals Connector (OSTI)

As a general rule, broad-band sources which employ projection optics are the most difficult to evaluate. In addition to the problems encountered in evaluating exposed lamps, one must characterize the projected...

David Sliney; Myron Wolbarsht

1980-01-01T23:59:59.000Z

408

Circle Project  

E-Print Network (OSTI)

This project asks students to decide if a collection of points in space do or do not lie on a ... The project is accessible to linear algebra students who have studied ...

409

Hydropower Projects  

Energy.gov (U.S. Department of Energy (DOE))

This report covers the Wind and Water Power Technologies Office's hydropower project funding from fiscal years 2008 to 2014.

410

Characterization of Friction Stir Welded Tubes by Means of Tube Bulge Test  

SciTech Connect

Mechanical properties of friction stir welded joints are generally evaluated by means of conventional tensile test. This testing method might provide insufficient information because maximum strain obtained in tensile test before necking is small; moreover, the application of tensile test is limited when the joint path is not linear or even when the welds are executed on curved surfaces. Therefore, in some cases, it would be preferable to obtain the joints properties from other testing methods. Tube bulge test can be a valid solution for testing circumferential or longitudinal welds executed on tubular workpieces. The present work investigates the mechanical properties and the formability of friction stir welded tubes by means of tube bulge tests. The experimental campaign was performed on tubular specimens having a thickness of 3 mm and an external diameter of 40 mm, obtained starting from two semi-tubes longitudinally friction stir welded. The first step, regarding the fabrication of tubes, was performed combining a conventional forming process and friction stir welding. Sheets in Al-Mg-Si-Cu alloy AA6060 T6 were adopted for this purpose. Plates having a dimension of 225x60 mm were bent (with a bending axis parallel to the main dimension) in order to obtain semi-tubes. A particular care was devoted to the fabrication of forming devices (punch and die) in order to minimize the springback effects. Semi-tubes were then friction stir welded by means of a CNC machine tool. Some preliminary tests were carried out by varying the welding parameters, namely feed rate and rotational speed. A very simple tool having flat shoulder and cylindrical pin was used. The second step of the research was based on testing the welded tubes by means of tube bulge test. A specific equipment having axial actuators with a conical shape was adopted for this study. Some analyses were carried out on the tubes bulged up to a certain pressure level. In particular, the burst pressure and the wall thickness were measured for each tested tube.

D'Urso, G.; Longo, M.; Giardini, C. [University of Bergamo-Dept. of Design and Technologies-Italy-Viale Marconi 5, 24044 Dalmine (Italy)

2011-05-04T23:59:59.000Z

411

Horizontal Beam Tubes - HFIR Technical Parameters | ORNL Neutron Sciences  

NLE Websites -- All DOE Office Websites (Extended Search)

Horizontal Beam Tubes Horizontal Beam Tubes The reactor has four horizontal beam tubes that supply the neutrons to the neutron scattering instruments. Details for each beam tube and instrument can be found on the HFIR instrument page. Each of the beam tubes that supply these instruments with neutrons is described subsequently. HB-1 and HB-3 The HB-1 and HB-3 thermal neutron beam tube designs are identical except for the length. Both are situated tangential to the reactor core so that the tubes point at reflector material and do not point directly at the fuel. An internal collimator is installed at the outboard end. This collimator is fabricated out of carbon steel and is plated with nickel. The collimator provides a 2.75-in by 5.5-in. rectangular aperture. A rotary shutter is located outboard of each of these beam tubes. The

412

Refrigerant forced-convection condensation inside horizontal tubes  

E-Print Network (OSTI)

Condensing heat transfer rates inside a horizontal tube were investigated -for large quality changes across the tube. The proposed correlation is a modification of the work of Rohsenow, Webber and Ling [29]. The result of ...

Bae, Soonhoon

1968-01-01T23:59:59.000Z

413

Corrosion Failure of an In-service Economizer Tube  

Science Journals Connector (OSTI)

This investigation was primarily aimed to examine the in-service failure of an economizer tube. Apart from preliminary visual examination, ... thickness hole in the weld region of the economizer tube. This water ...

H. Roy; P. Sharma; D. Ghosh; A. K. Shukla

2014-08-01T23:59:59.000Z

414

Delayed hydride cracking behavior for ZIRCALOY-2 tubing  

Science Journals Connector (OSTI)

The delayed hydride cracking (DHC) behavior for ZIRCALOY-2 tubing was characterized at temperatures ranging from 93 °C to 288 °C. Testing was performed on the three types of pressure tubes that were used in th...

F. H. Huang; W. J. Mills

1991-09-01T23:59:59.000Z

415

Power Projects  

NLE Websites -- All DOE Office Websites (Extended Search)

Power Projects Power Projects Contact SN Customers Environmental Review-NEPA Operations & Maintenance Planning & Projects Power Marketing Rates You are here: SN Home page > About SNR Power Projects Central Valley: In California's Central Valley, 18 dams create reservoirs that can store 13 million acre-feet of water. The project's 615 miles of canals irrigate an area 400 miles long and 45 miles wide--almost one third of California. Powerplants at the dams have an installed capacity of 2,099 megawatts and provide enough energy for 650,000 people. Transmission lines total about 865 circuit-miles. Washoe: This project in west-central Nevada and east-central California was designed to improve the regulation of runoff from the Truckee and Carson river systems and to provide supplemental irrigation water and drainage, as well as water for municipal, industrial and fishery use. The project's Stampede Powerplant has a maximum capacity of 4 MW.

416

ORIGINAL ARTICLE Yield prediction for seamless tubing processes  

E-Print Network (OSTI)

tubing process 1 Introduction Pipe products made from carbon and alloy steel are commonly used in oil and natural gas exploration and production, fluid transmission, and the construction indus- try. A market an increasing demand for seamless tubing for gas and oil production [1]. Steel tubes are made by several

Huang, Samuel H.

417

Instability characteristics of fluidelastic instability of tube rows in crossflow  

SciTech Connect

An experimental study is reported to investigate the jump phenomenon in critical flow velocities for tube rows with different pitch-to-diameter ratios and the excited and intrinsic instabilities for a tube row with a pitch-to-diameter ratio of 1.75. The experimental data provide additional insights into the instability phenomena of tube arrays in crossflow. 9 refs., 10 figs.

Chen, S.S.; Jendrzejczyk, J.A.

1986-04-01T23:59:59.000Z

418

ACCELERATOR TUBES H. R. McK. HYDER  

E-Print Network (OSTI)

ACCELERATOR TUBES H. R. McK. HYDER Nuclear Physics Laboratory, University of Oxford, Oxford OX1 3RH The characteristics and performance of accelerator tubes required by the new generation of large tandem accelerators conclusions are drawn about future progress and developments. ACCELERATOR TUBES AND INSULATORS. 1

Paris-Sud XI, Université de

419

Department of Mechanical Engineering Spring 2010 Wellbore Coil Tubing  

E-Print Network (OSTI)

PENNSTATE Department of Mechanical Engineering Spring 2010 Wellbore Coil Tubing Overview In BP reaching the bottom of the wellbore utilizing a pre- loaded constant force spring. The coiled tubing's North American Gas Division, there are approximately 800 wellbores with coiled tubing installed

Demirel, Melik C.

420

Finned Tube With Vortex Generators For A Heat Exchanger.  

DOE Patents (OSTI)

A system for and method of manufacturing a finned tube for a heat exchanger is disclosed herein. A continuous fin strip is provided with at least one pair of vortex generators. A tube is rotated and linearly displaced while the continuous fin strip with vortex generators is spirally wrapped around the tube.

Sohal, Monohar S. (Idaho Falls, ID); O'Brien, James E. (Idaho Falls, ID)

2004-09-14T23:59:59.000Z

Note: This page contains sample records for the topic "tube project decommissioning" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


421

Source Terms for HFIR Beam Tube Shielding Analyses, and a Complete Shielding Analysis of the HB-3 Tube  

SciTech Connect

The High Flux Isotope Reactor (HFIR) at the Oak Ridge National Laboratory is in the midst of a massive upgrade program to enhance experimental facilities. The reactor presently has four horizontal experimental beam tubes, all of which will be replaced or redesigned. The HB-2 beam tube will be enlarged to support more guide tubes, while the HB-4 beam tube will soon include a cold neutron source.

Bucholz, J.A.

2000-07-01T23:59:59.000Z

422

Helium-filled aluminum flight tubes  

NLE Websites -- All DOE Office Websites (Extended Search)

Helium-filled aluminum flight tubes. Helium-filled aluminum flight tubes. Detector housing for the CCD camera lens, mirror, and scintillator. For more information, contact Instrument Scientist: Hassina Bilheux, bilheuxhn@ornl.gov, 865.384.9630 neutrons.ornl.gov/instruments/HFIR/factsheets/Instrument-cg1d.pdf The CG-1D beam is used for neutron imaging measurements using a white beam. Apertures (with different diameters D (pinhole geometry) are used at the entrance of the helium-filled flight path to allow L/D variation from 400 to 800. L is the distance between the aperture and the detector (where the image is produced). Samples sit on a translation/ rotation stage for alignment and tomography purposes. Detectors for CG-1D include

423

Color Magnetic Flux Tubes in Dense QCD  

E-Print Network (OSTI)

QCD is expected to be in the color-flavor locking phase in high baryon density, which exhibits color superconductivity. The most fundamental topological objects in the color superconductor are non-Abelian vortices which are topologically stable color magnetic flux tubes. We present numerical solutions of the color magnetic flux tube for diverse choices of the coupling constants. We also analytically study its asymptotic profiles and find that they are different from the case of usual superconductors. We propose the width of color magnetic fluxes and find that it is larger than naive expectation of the Compton wave length of the massive gluon when the gluon mass is larger than the scalar mass.

Minoru Eto; Muneto Nitta

2009-07-07T23:59:59.000Z

424

Color magnetic flux tubes in dense QCD  

SciTech Connect

QCD is expected to be in the color-flavor locking phase in high baryon density, which exhibits color superconductivity. The most fundamental topological objects in the color superconductor are non-Abelian vortices which are topologically stable color magnetic flux tubes. We present numerical solutions of the color magnetic flux tube for diverse choices of the coupling constants based on the Ginzburg-Landau Lagrangian. We also analytically study its asymptotic profiles and find that they are different from the case of usual superconductors. We propose the width of color magnetic fluxes and find that it is larger than naive expectation of the Compton wavelength of the massive gluon when the gluon mass is larger than the scalar mass.

Eto, Minoru [Theoretical Physics Laboratory, RIKEN, Saitama 351-0198 (Japan); Nitta, Muneto [Department of Physics, and Research and Education Center for Natural Sciences, Keio University, 4-1-1 Hiyoshi, Yokohama, Kanagawa 223-8521 (Japan)

2009-12-15T23:59:59.000Z

425

Coupled-cavity drift-tube linac  

DOE Patents (OSTI)

A coupled-cavity drift-tube linac (CCDTL) combines features of the Alvarez drift-tube linac (DTL) and the {pi}-mode coupled-cavity linac (CCL). In one embodiment, each accelerating cavity is a two-cell, 0-mode DTL. The center-to-center distance between accelerating gaps is {beta}{lambda}, where {lambda} is the free-space wavelength of the resonant mode. Adjacent accelerating cavities have oppositely directed electric fields, alternating in phase by 180 degrees. The chain of cavities operates in a {pi}/2 structure mode so the coupling cavities are nominally unexcited. The CCDTL configuration provides an rf structure with high shunt impedance for intermediate velocity charged particles, i.e., particles with energies in the 20-200 MeV range. 5 figs.

Billen, J.H.

1996-11-26T23:59:59.000Z

426

Decommissioning of the remediation systems at Waverly, Nebraska, in 2011-2012.  

SciTech Connect

The Commodity Credit Corporation of the U.S. Department of Agriculture (CCC/USDA) operated a grain storage facility in Waverly, Nebraska, from 1952 to 1974. During this time, the grain fumigant '80/20' (carbon tetrachloride/carbon disulfide) was used to preserve stored grain. In 1982, sampling by the U.S. Environmental Protection Agency (EPA) found carbon tetrachloride contamination in the town's groundwater. After an investigation of the contaminant distribution, the site was placed on the National Priority List (NPL) in 1986, and the CCC/USDA accepted responsibility for the contamination. An Interagency Compliance Agreement between the EPA and the CCC/USDA was finalized in May 1988 (EPA 1990). The EPA (Woodward-Clyde Consultants, contractor) started immediate cleanup efforts in 1987 with the installation of an air stripper, a soil vapor extraction system, a groundwater extraction well, and groundwater and soil gas monitoring wells (Woodward-Clyde 1986, 1988a,b). After the EPA issued its Record of Decision (ROD; EPA 1990), the CCC/USDA (Argonne National Laboratory, contractor) took over operation of the treatment systems. The CCC/USDA conducted a site investigation (Argonne 1991, 1992a,b), during which a carbon tetrachloride plume in groundwater was discovered northeast of the former facility. This plume was not being captured by the existing groundwater extraction system. The remediation system was modified in 1994 (Argonne 1993) with the installation of a second groundwater extraction well to contain the contamination further. Subsequently, a detailed evaluation of the system resulted in a recommendation to pump only the second well to conserve water in the aquifer (Argonne 1995). Sampling and analysis after implementation of this recommendation showed continued decreases in the extent and concentrations of the contamination with only one well pumping (Argonne 1999). The CCC/USDA issued quarterly monitoring reports from 1988 to 2009. Complete documentation of the CCC/USDA characterization and remediation efforts, including the quarterly monitoring reports, is on the compact disc inside the back cover of this report. The EPA reported on the progress of the remediation systems in a series of five-year reviews (EPA 1993, 1999, 2004, 2009). These reports and other EPA documentation are also on the compact disc inside the back cover of this report, along with the Woodward-Clyde (1986, 1988a,b) documentation cited. Starting in 2006, the analytical results for groundwater (the only medium still being monitored) showed no carbon tetrachloride concentrations above the maximum contaminant level (MCL) of 5.0 g/L. Because the cleanup goals specified in the ROD (EPA 1990) had been met, the EPA removed the site from the NPL in November 2006 (Appendix A). In 2008 the National Pollutant Discharge Elimination System (NPDES) permit for the remediation system was deactivated, and a year later the EPA released its fourth and final five-year report (EPA 2009), indicating that no further action was required for the site and that the site was ready for unlimited use. In 2011-2012, the CCC/USDA decommissioned the remediation systems at Waverly. This report documents the decommission process and closure of the site.

LaFreniere, L. M. (Environmental Science Division)

2012-06-29T23:59:59.000Z

427

Stable sonoluminescence within a water hammer tube  

Science Journals Connector (OSTI)

The sonoluminescence (SL) from the collapse of a single gas bubble within a liquid can be produced repetitively using an acoustic resonator. An alternative technique using a water hammer tube, producing SL from bubbles of greater size, is described here. A sealed vertical tube partly filled with a liquid and a gas at low pressure is subjected to vertical vibrations. The oscillation of the pressure within the liquid column, due to inertial forces, excites cavitation bubbles to grow and collapse. Rotation is used to confine the bubbles to the axis of the tube. Bright SL emissions were observed in a number of liquids. Repetitive emission was produced from bubbles in condensed phosphoric acid. Bubbles of 0.4mm ambient radius (containing 2×1014 xenon atoms) were excited by vibration at 35Hz. Approximately 1012 photons were emitted per collapse in the range 400–700nm (over four orders of magnitude greater than the brightest SL reported previously), corresponding to a 1% efficiency of the conversion of mechanical energy into light.

Avik Chakravarty; Theo Georghiou; Tacye E. Phillipson; Alan J. Walton

2004-06-24T23:59:59.000Z

428

Preliminary standard review guide for Environmental Restoration/Decontamination and Decommissioning safety analyses  

SciTech Connect

The review guide is based on the shared experiences, approaches, and philosophies of the Environmental Restoration/Decontamination and Decommissioning (ER/D&D) subgroup members. It is presented in the form of a review guide to maximize the benefit to both the safety analyses practitioner and reviewer. The guide focuses on those challenges that tend to be unique to ER/D&D cleanup activities. Some of these experiences, approaches, and philosophies may find application or be beneficial to a broader spectrum of activities such as terminal cleanout or even new operations. Challenges unique to ER/D&D activities include (1) consent agreements requiring activity startup on designated dates; (2) the increased uncertainty of specific hazards; and (3) the highly variable activities covered under the broad category of ER/D&D. These unique challenges are in addition to the challenges encountered in all activities; e.g., new and changing requirements and multiple interpretations. The experiences in approaches, methods, and solutions to the challenges are documented from the practitioner and reviewer`s perspective, thereby providing the viewpoints on why a direction was taken and the concerns expressed. Site cleanup consent agreements with predetermined dates for restoration activity startup add the dimension of imposed punitive actions for failure to meet the date. Approval of the safety analysis is a prerequisite to startup. Actions that increase expediency are (1) assuring activity safety; (2) documenting that assurance; and (3) acquiring the necessary approvals. These actions increase the timeliness of startup and decrease the potential for punitive action. Improvement in expediency has been achieved by using safety analysis techniques to provide input to the line management decision process rather than as a review of line management decisions. Expediency is also improved by sharing the safety input and resultant decisions with reviewers and regulators.

Ellingson, D.R.

1993-06-01T23:59:59.000Z

429

Project Title  

NLE Websites -- All DOE Office Websites (Extended Search)

CCS CCS August 20-22, 2013 2 Presentation Outline * Benefits to the program * Project overall objectives * Technical status * Project summary * Conclusions and future plans 3 Benefit to the Program * Develop technologies that will support industries' ability to predict CO 2 storage capacity in geologic formations to within ±30 percent. * Develop technologies to demonstrate that 99 percent of injected CO 2 remains in the injection zones. * This research project develops a reservoir scale CO 2 plume migration model at the Sleipner project, Norway. The Sleipner project in the Norwegian North Sea is the world's first commercial scale geological carbon storage project. 4D seismic data have delineated the CO 2 plume migration history. The relatively long history and high fidelity data make

430

Report on waste burial charges. Escalation of decommissioning waste disposal costs at low-level waste burial facilities, Revision 4  

SciTech Connect

One of the requirements placed upon nuclear power reactor licensees by the U.S. Nuclear Regulatory Commission (NRC) is for the licensees to periodically adjust the estimate of the cost of decommissioning their plants, in dollars of the current year, as part of the process to provide reasonable assurance that adequate funds for decommissioning will be available when needed. This report, which is scheduled to be revised periodically, contains the development of a formula for escalating decommissioning cost estimates that is acceptable to the NRC. The sources of information to be used in the escalation formula are identified, and the values developed for the escalation of radioactive waste burial costs, by site and by year, are given. The licensees may use the formula, the coefficients, and the burial escalation factors from this report in their escalation analyses, or they may use an escalation rate at least equal to the escalation approach presented herein. This fourth revision of NUREG-1307 contains revised spreadsheet results for the disposal costs for the reference PWR and the reference BWR and the ratios of disposal costs at the Washington, Nevada, and South Carolina sites for the years 1986, 1988, 1991 and 1993, superseding the values given in the May 1993 issue of this report. Burial cost surcharges mandated by the Low-Level Radioactive Waste Policy Amendments Act of 1985 (LLRWPAA) have been incorporated into the revised ratio tables for those years. In addition, spreadsheet results for the disposal costs for the reference reactors and ratios of disposal costs at the two remaining burial sites in Washington and South Carolina for the year 1994 are provided. These latter results do not include any LLRWPAA surcharges, since those provisions of the Act expired at the end of 1992. An example calculation for escalated disposal cost is presented, demonstrating the use of the data contained in this report.

Not Available

1994-06-01T23:59:59.000Z

431

Report on waste burial charges: Escalation of decommissioning waste disposal costs at Low-Level Waste Burial facilities. Revision 5  

SciTech Connect

One of the requirements placed upon nuclear power reactor licensees by the US Nuclear Regulatory Commission (NRC) is for the licensees to periodically adjust the estimate of the cost of decommissioning their plants, in dollars of the current year, as part of the process to provide reasonable assurance that adequate funds for decommissioning will be available when needed. This report, which is scheduled to be revised periodically, contains the development of a formula for escalating decommissioning cost estimates that is acceptable to the NRC. The sources of information to be used in the escalation formula are identified, and the values developed for the escalation of radioactive waste burial costs, by site and by year, are given. The licensees may use the formula, the coefficients, and the burial escalation factors from this report in their escalation analyses, or they may use an escalation rate at least equal to the escalation approach presented herein. This fifth revision of NUREG-1307 contains revised spreadsheet results for the disposal costs for the reference PWR and the reference BWR and the ratios of disposal costs at the Washington, Nevada, and South Carolina sites for the years 1986, 1988, 1991, 1993, and 1994, superseding the values given in the June 1994 issue of this report. Burial cost surcharges mandated by the Low-Level Radioactive Waste Policy Amendments Act of 1985 (LLRWPAA) have been incorporated into the revised ratio tables for those years. In addition, spreadsheet results for the disposal costs for the reference reactors and ratios of disposal costs at the two remaining burial sites in Washington and South Carolina for the year 1995 are provided. These latter results do not include any LLRWPAA surcharges, since those provisions of the Act expired at the end of 1992. An example calculation for escalated disposal cost is presented, demonstrating the use of the data contained in this report.

NONE

1995-08-01T23:59:59.000Z

432

Segmented lasing tube for high temperature laser assembly  

DOE Patents (OSTI)

A high temperature laser assembly capable of withstanding operating temperatures in excess of 1500.degree. C. is described comprising a segmented cylindrical ceramic lasing tube having a plurality of cylindrical ceramic lasing tube segments of the same inner and outer diameters non-rigidly joined together in axial alignment; insulation of uniform thickness surround the walls of the ceramic lasing tube; a ceramic casing, preferably of quartz, surrounding the insulation; and a fluid cooled metal jacket surrounds the ceramic casing. In a preferred embodiment, the inner surface of each of the ceramic lasing tube segments are provided with a pair of oppositely spaced grooves in the wall thereof parallel to the center axis of the segmented cylindrical ceramic lasing tube, and both of the grooves and the center axis of the segmented cylindrical ceramic lasing tube lie in a common plane, with the grooves in each ceramic lasing tube segment in circumferential alignment with the grooves in the adjoining ceramic lasing tube segments; and one or more ceramic plates, all lying in a common plane to one another and with the central axis of the segmented ceramic lasing tube, are received in the grooves to provide additional wall area in the segmented ceramic lasing tube for collision and return to ground state of metastable metal atoms within the segmented ceramic lasing tube.

Sawicki, Richard H. (Danville, CA); Alger, Terry W. (Tracy, CA); Finucane, Raymond G. (Pleasanton, CA); Hall, Jerome P. (Livermore, CA)

1996-01-01T23:59:59.000Z

433

Project Title  

NLE Websites -- All DOE Office Websites (Extended Search)

Test and Evaluation of Test and Evaluation of Engineered Biomineralization Technology for Sealing Existing wells Project Number: FE0009599 Robin Gerlach Al Cunningham, Lee H Spangler Montana State University U.S. Department of Energy National Energy Technology Laboratory Carbon Storage R&D Project Review Meeting Developing the Technologies and Infrastructure for CCS August 20-22, 2013 Presentation Outline * Motivation & Benefit to the Program (required) * Benefit to the Program and Project Overview (required) * Background information - Project Concept (MICP) - Ureolytic Biomineralization, Biomineralization Sealing * Accomplishments to Date - Site Characterization - Site Preparation - Experimentation and Modeling - Field Deployable Injection Strategy Development * Summary

434

Project Title  

NLE Websites -- All DOE Office Websites (Extended Search)

LBNL's Consolidated Sequestration Research Program (CSRP) Project Number FWP ESD09-056 Barry Freifeld Lawrence Berkeley National Laboratory U.S. Department of Energy National Energy Technology Laboratory Carbon Storage R&D Project Review Meeting Developing the Technologies and Infrastructure for CCS August 20-22, 2013 2 Presentation Outline * Benefits and Goals of GEO-SEQ * Technical Status - Otway Project (CO2CRC) - In Salah (BP, Sonatrach and Statoil) - Ketzin Project (GFZ, Potsdam) - Aquistore (PTRC) * Accomplishments and Summary * Future Plans 3 Benefit to the Program * Program goals being addressed: - Develop technologies to improve reservoir storage capacity estimation - Develop and validate technologies to ensure 99 percent storage permanence.

435

Project Title  

NLE Websites -- All DOE Office Websites (Extended Search)

1-23, 2012 1-23, 2012 2 Presentation Outline I. Benefits II. Project Overview III. Technical Status A. Background B. Results IV. Accomplishments V. Summary 3 Benefit to the Program * Program goals. - Prediction of CO 2 storage capacity. * Project benefits. - Workforce/Student Training: Support of 3 student GAs in use of multiphase flow and geochemical models simulating CO 2 injection. - Support of Missouri DGLS Sequestration Program. 4 Project Overview: Goals and Objectives Project Goals and Objectives. 1. Training graduate students in use of multi-phase flow models related to CO 2 sequestration. 2. Training graduate students in use of geochemical models to assess interaction of CO

436

Project Title  

NLE Websites -- All DOE Office Websites (Extended Search)

Center for Coal's Center for Coal's FY10 Carbon Sequestration Peer Review February 8 - 12, 2010 2 Collaborators * Tissa Illangasekare (Colorado School of Mines) * Michael Plampin (Colorado School of Mines) * Jeri Sullivan (LANL) * Shaoping Chu (LANL) * Jacob Bauman (LANL) * Mark Porter (LANL) 3 Presentation Outline * Benefit to the program * Project overview * Project technical status * Accomplishments to date * Future Plans * Appendix 4 Benefit to the program * Program goals being addressed (2011 TPP): - Develop technologies to demonstrate that 99 percent of injected CO 2 remains in the injection zones. * Project benefit: - This project is developing system modeling capabilities that can be used to address challenges associated with infrastructure development, integration, permanence &

437

Discontinued Projects  

Energy.gov (U.S. Department of Energy (DOE))

This page lists projects that received a loan or a loan guarantee from DOE, but that are considered discontinued by LPO for one of several reasons.

438

project management  

National Nuclear Security Administration (NNSA)

the Baseline Change Proposal process. Two 400,000-gallon fire protection water supply tanks and associated pumping facilities were added. Later in the project, an additional...

439

Custom Projects  

NLE Websites -- All DOE Office Websites (Extended Search)

and Incentive Payment - The ESIP works with utility, industry, and BPA to complete the measurement and verification, reporting and development of a custom project completion...

440

EIS-0259 Final Environmental Impact Statement On The Disposal Of Decommissioned, Defueled Cruiser, Ohio Class, And Los Angeles Class Naval Reactor Plants  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

-. -. 1. PURPOSE AND NEED U.S. Navy nuclear ships are decommissioned and defieled at the end of their usefi Metime, when the cost of continued operation is not justified by their fitary capabfity, or when the ship is no longer needed. The Navy needs to disposition the reactor compartments born defieled and decommissioned ctisers, and OHIO Class and LOS ANGELES Class submarines. The number of reactor compartments under consideration by this Environmental Impact Statement is about 100. These reactor compartments are in addition to the pre-LOS ANGELES Class submarines tieady being disposed of under the Na&s 1984 Find Environmental hpact Statement (USN, 1984a). Newer types of U.S. Navy nuclear-powered stips that are not expected to be decommissioned in the next 20 years (e.g., aircraft carriers, SEAWOLF Class submarines) are not included in this fid Enviromentd Impact Statement.

Note: This page contains sample records for the topic "tube project decommissioning" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.